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Attachment 5 - Gpu Nuclear Calculation 4440-7380-90-017, Revision 3, Pdms SAR Section 8.2.5 Fire Analysis Source Terms
	ML22105A092
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Site:	Three Mile Island
Issue date:	04/08/2022
From:	; TMI-2 Solutions
To:	; Office of Nuclear Material Safety and Safeguards
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Attachment 5 TMl2-RA-COR-2022-0007 License Amendment Request Three Mile Island Nuclear Station, Unit 2 "GPU Nuclear Calculation 4440-7380-90-017, Revision 3, PDMS SAR Section 8.2.5 Fire Analysis Source Terms" (PROPRIETARY)

CC-AA-309-1001 Revision 9 ATTACHMENT 1 Design Analysis Cover Sheet Page 1 0 f5 Design Analysis I Last Page No. ' C4 Revision:

Analysis No.: 1 4440-7380-90-017 32 3 Major 0 Minor D

Title:

, PDMS SAR Section 8.2.5 Fire Analysis Source Terms EC No.:' 0000626787 Revision:* 0 Station(s): 1 Three Mile Island Component(s): 1 Unit No.:' 2 Discipline: ' N/A Descrip. Code/Keyword: 10 N/A Safety/QA Class: 11 Safety Related System Code: 12 N/A Structure: 13 N/A CONTROLLED DOCUMENT REFERENCES 1 Document No.: From/To Document No.: From/To PDMS SAR Section H8.2.5 To 4440-7380-90-017 Rev 0 From 4440-7380-90-017 Rev 2 From

87-008 From Is this Design Analysis Safeguards Information? 1

Yes No0 If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? Yes No0 If yes, ATI/AR#:

17 This Design Analysis SUPERCEDES: " 4440-7380-90-017 Revision 2 in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): 1 The purpose of this revision is to 1) update source terms to account for 26 years of decay, 2) update source terms to account for additional loose contamination, 3) use FGR 11 and FGR 12 dose conversion factors, and 4) calculate doses using TEDE methodology for comparison to current regulatory and plant administrative dose limits.

All pages replaced. Added pages I-Iv, 1-17, A1-A83, 81-82, G 1 - G 4 c £ " ! 5 L Preparer: 20 Harley D. Hutchins (S&L) 4/5/2019 Print Name ---, SIAn Name Date Method of Review: 21 Detailed Review 0 Alternate Ca~ationspzhed) D Testing D Reviewer: 22 Anthony Klazura (S&L)

Print Name (2 (j

,,4 ~-

Sign !)fame

"//_0Jv/1f I 0ate Review Notes: 23 Independent review 0 Peer review D (For External Analyses Only)

External Approver: " Anthony Klazura (S&L)

Print Name Sign Name Date Exelon Reviewer: "

Print Name Sign Name Date Independent 3 rd Party Review Reqd? 26 Yes No Exelon Approver: 21 Pnnt Name Sian Name Date Page i

CC-AA-309-1001 Revision 9 ATTACHMENT 2 Owner's Acceptance Review Checklist for External Design Analyses Page 1 of3 Design Analysis No.: 4440-7380-90-017 Rev: 3 No Question Instructions and Guidance Yes/No/N/A 1 Do assumptions have sufficient documented All Assumptions should be stated in clear terms with enough justification to confirm that the assumption is conservative.

rationale?

For example, 1) the exact value of a particular parameter may not be known or that parameter may be known to vary over the range of conditions covered by the Calculation. It is appropriate to represent or bound the parameter with an assumed value. 2) The predicted performance of a specific piece of equipment in lieu of actual test data. It is appropriate to use the documented opinion/position of a recognized expert on that equipment to represent predicted equipment performance.

Consideration should also be given as to any qualification testing that may be needed to validate the Assumptions. Ask yourself, would you provide more justification if you were performing this analysis? If yes, the rationale is likely incomplete.

2 Are assumptions compatible with the way Ensure the documentation for source and rationale for the assumption supports the way the plant is currently or will be the plant is operated and operated post change and they are not in conflict with any design with the licensing basis? parameters. If the Analysis purpose is to establish a new licensing basis, this question can be answered yes, if the assumption supports that new basis.

3 Do all unverified assumptions have a If there are unverified assumptions without a tracking mechanism indicated, then create the tracking item either through an A TI or a tracking and closure work order attached to the implementing WO. Due dates for these mechanism in place? actions need to support verification prior to the analysis becoming operational or the resultant plant change being op authorized.

4 Do the design inputs have sufficient rationale?

The origin of the input, or the source should be identified and be readily retrievable within Exelon' s documentation system. If not, then the source should be attached to the analysis. Ask yourself, would you provide more justification if you were performing this analysis? If yes, the rationale is likely incomplete.

5 Are design inputs correct and reasonable with The expectation is that an Exelon Engineer should be able to clearly understand which input parameters are critical to the outcome of the critical parameters analysis. That is, what is the impact of a change in the parameter to identified, if appropriate? the results of the analysis? If the impact is large, then that parameter is critical.

6 Are design inputs compatible with the way Ensure the documentation for source and rationale for the inputs supports the way the plant is currently or will be operated post the plant is operated and change and they are not in conflict with any design parameters.

with the licensing basis?

Page ii

CC-AA-309-1001 Revision 9 ATTACHMENT 2 Owner's Acceptance Review Checklist for External Design Analyses Page 2 of3 Design Analysis No.: 4440-7380-90-017 Rev: 3 No Question Instructions and Guidance Yes /No/ NIA 7 Are Engineering Judgments clearly See Section 2.13 in CC-AA-309 for the attributes that are sufficient to justify Engineering Judgment. Ask yourself, would documented and justified? you provide more justification if you were performing this analysis? If yes, the rationale is likely incomplete.

8 Are Engineering Judgments compatible with Ensure the justification for the engineering judgment supports the way the plant is currently or will be operated post change and is the way the plant is not in conflict with any design parameters. If the Analysis operated and with the purpose is to establish a new licensing basis, then this question licensing basis? can be answered yes, if the judgment supp01is that new basis.

9 Do the results and conclusions satisfy the Why was the analysis being performed? Does the stated purpose match the expectation from Exelon on the proposed application of purpose and objective of the results? If yes, then the analysis meets the needs of the the Design Analysis? contract.

10 Are the results and conclusions compatible Make sure that the results support the UFSAR defined system design and operating conditions, or they support a proposed with the way the plant is change to those conditions. If the analysis supports a change, are operated and with the all of the other changing documents included on the cover sheet as licensing basis? impacted documents?

11 Have any limitations on the use of the results been Does the analysis support a temporary condition or procedure change? Make sure that any other documents needing to be identified and transmitted updated are included and clearly delineated in the design analysis.

to the appropriate Make sure that the cover sheet includes the other documents where organizations? the results of this analysis provide the input.

12 Have margin impacts been identified and documented Make sure that the impacts to margin are clearly shown within the body of the analysis. If the analysis results in reduced margins appropriately for any ensure that this has been appropriately dispositioned in the EC negative impacts being used to issue the analysis.

(Reference ER-AA-2007)?

13 Does the Design Analysis include the applicable Are there sufficient documents included to support the sources of input, and other reference material that is not readily retrievable in design basis Exelon controlled Documents?

documentation?

14 Have all affected design analyses been documented Determine if sufficient searches have been performed to identify any related analyses that need to be revised along with the base on the Affected Documents analysis. It may be necessary to perform some basic searches to List (ADL) for the validate this.

associated Configuration Change?

15 Do the sources of inputs and analysis methodology Compare any referenced codes and standards to the current design basis and ensure that any differences are reconciled. If the input used meet committed sources or analysis methodology are based on an out-of-date technical and regulatory methodology or code, additional reconciliation may be required if requirements? the site has since committed to a more recent code Page iii

CC-AA-309-1001 Revision 9 ATTACHMENT 2 Owner's Acceptance Review Checklist for External Design Analyses Page 3 of3 Design Analysis No.: 4440-7380-90-017 Rev: 3 No Question Instructions and Guidance Yes /No /NIA 16 Have vendor supporting technical documents and Based on the risk assessment performed during the pre-job brief for the analysis (per HU-AA-1212), ensure that sufficient reviews references (including GE of any supporting documents not provided with the final analysis DRFs) been reviewed are performed.

when necessarv?

17 Do operational limits support assumptions and Ensure the Tech Specs, Operating Procedures, etc. contain operational limits that support the analysis assumptions and inputs? inputs.

List the critical characteristics of the product, and validate those critical characteristics.

18.

Create an SFMS entry as required by CC-AA-4008. SFMS Number: _ _ _ _ _ _ _ __

Page iv

4440-7380-90-017, Revision 3 Page 1 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Table of Contents Coversheet ..................................................................................................................................................... i Owner's Acceptance Review Checklist ........................................................................................................ ii Table of Contents .......................................................................................................................................... 1 1.0 Purpose .............................................................................................................................................. 2 1.1 Acceptance Criteria ....................................................................................................................... 2 2.0 Inputs ................................................................................................................................................ 3 2.1 Source Terms ................................................................................................................................ 3 2.2 Dose Conversion Factors .............................................................................................................. 3 2.3 Chi/Q Value .................................................................................................................................. 4 2.4 Breathing Rate .............................................................................................................................. 4 2.5 Radionuclide Decay Schemes and Decay Constants .................................................................... 4 2.6 Plume Release Time ...................................................................................................................... 5 3.0 Assu1nptions ...................................................................................................................................... 5 3.1 Deterministic Nature of Fires ........................................................................................................ 5 3.2 Activity Released as Particulate .................................................................................................... 5 3.3 No Credit for Plateout ................................................................................................................... 5 3.4 HEPA Efficiency .......................................................................................................................... 5 3.5 Automatic Isolation of Reactor Building Breather Line ............................................................... 5 3.6 Particle Size of Source Term Particulates ..................................................................................... 5 3.7 Chemical Form of Plutonium ........................................................................................................ 5 3.8 Case 1 Assumptions ...................................................................................................................... 5 3.9 Case 2 Assumptions ...................................................................................................................... 6 3.10 Case 3 Assumptions ...................................................................................................................... 6 4.0 References ......................................................................................................................................... 6 5.0 Identification of Computer Programs ............................................................................................... 6 6.0 Method of Analysis ........................................................................................................................... 7 6.1 PDMS Unanticipated Events ........................................................................................................ 7 6.2 Case 1: Reactor Building Purge System Operating ...................................................................... 7 6.3 Case 2: Reactor Building at Negative Pressure ............................................................................. 7 6.4 Case 3: Reactor Building under Passive Ventilation .................................................................... 8 6.5 Source Term Modification ............................................................................................................ 8 7.0 Numeric Analysis ............................................................................................................................. 9 7.1 Source Term Determination .......................................................................................................... 9 7.2 Case 1 Analysis ........................................................................................................................... 11 8.0 Results ............................................................................................................................................. 16 8.1 Case 1 Results ............................................................................................................................. 16 8.2 Case 2 Results ............................................................................................................................. 16 8.3 Case 3 Results ............................................................................................................................. 17 9.0 Conclusions ..................................................................................................................................... 17 10.0 Attachments .................................................................................................................................... 17

4440-7380-90-017, Revision 3 Page 2 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 1.0 PURPOSE The purpose of this engineering analysis is to assess the dose to the public due to a fire in the containment of Unit 2 of the Three Mile Island Nuclear Station (TMl-2). The plant is in Post Defueling Monitored Storage (PDMS) mode. To the extent possible, combustibles, ignition sources, and radiation sources have been removed from the containment structure. However, some combustibles, ignition sources, and radioactive materials remain. Although the risk of fire in the containment during PDMS is very small, there is a possibility that some personnel error or electrical short could lead to a limited fire.

The analysis considers fires in the four distinct areas in the reactor building: The operating deck (OP),

The A & B D-Rings (ABD), The Fuel Transfer Channel (FTC), and the basement area (BAS). The analysis considers three fire scenarios: A fire while reactor building purge is running (Case 1), a fire while the reactor building is being held at a slightly negative pressure (Case 2), and a fire while the reactor building is under passive ventilation (Case 3). Total Effective Dose Equivalent (TEDE) and acute organ doses are calculated. These doses are compared to appropriate regulatory and administrative limits.

The objectives of this revision (Revision 3) of the engineering analysis are as follows:

1. Update the source terms to account for 26 years of decay (1992 - 2018)

2. Update the source terms to account for additional loose contamination

3. Use Federal Guidance Report 11 and Federal Guidance Report 12 dose conversion factors

4. Calculate TEDE and compare to current regulatory limits for TEDE and organ dose This revision of the engineering analysis is implemented via Engineering Change #0000626787.

1. I Acceptance Criteria A variety of federal postings dictate limits on radiation dose to the public for licensed nuclear power plants. These prescribed limits form the acceptance criteria for the doses calculated in this analysis.

Title 10 of the Code of Federal Regulations Part 20 (10 CFR 20 [Ref. 4.15]) establishes protection against ionizing radiation. In sections 20.130l(a)(l) and 20.130l(a)(2), dose rate limits for individual members of the public are established as 0.1 rem (100 mrem) TEDE annually or 0.002 rem (2 mrem) TEDE per hour. These dose limits apply for normal plant operation.

The criteria for siting a nuclear reactor are outlined in 10 CFR 100 [Ref. 4.16]. In section 100.1 l(a)(l),

the criteria for defining the exclusion zone around a reactor is based on the dose to an individual at the boundary of the exclusion zone due to a postulated release of fission products. The dose limit is denoted as 25 rem whole body (TEDE) or a 300 rem dose to the thyroid from iodine exposure. For the purpose of this calculation, the iodine-thyroid limit is considered applicable to any organ dose from any radionuclide (or combination ofradionuclides). There is no expectation that 10 CFR 100 dose limits will be exceeded.

More restrictive criteria for certain accident sequences have been promulgated in Chapter 15 of the NRC Standard Review Plan (NUREG-0800 [Ref. 4.17]). Specifically, the consequences of any accident must be 'well within' (i.e., less than 25%) or a 'small fraction' (less than 10%) of 10 CFR 100.

The EPA publishes guidelines for protective actions to take in response to a nuclear incident in their Protective Action Guide Manual [Ref. 4.18]. The level and extent of actions that must be taken to protect the public is determined by the projected dose to the individual as a result of the nuclear incident. The lowest dose that would prompt a protective action is 1 rem (prompting an evacuation or sheltering in place). Thus it is desirable to ensure no radiological release at TMl-2 exceeds 1 rem to the public.

The TMI-2 fire doses are significantly below these regulatory limits and EPA guidelines (see Revision 2 of this analysis). Therefore administrative limits are established as the PDMS standard. The potential offsite radiological dose resulting from postulated off-normal conditions, including fire, is required by the plant to be within the 10 CFR 50 Appendix I guidelines [Ref. 4.1 OJ. Appendix I of 10 CFR 50 presents guidelines for limiting dose consequences to as low as reasonably achievable. The administrative limit for

4440-7380-90-017, Revision 3 Page 3 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms offsite gaseous dose during PDMS is 5 mrem TEDE or 15 mrem to any organ. This very restrictive administrative application of 10 CFR 50 Appendix I guidance ensures that TMI-2 is demonstrably safe with respect to radiological implications.

2.0 INPUTS 2.1 Source Terms The source terms used in Revision 2 of this analysis (dated 1992) are presented in Reference 4.3.

Table 1. TMI-2 PDMS 1992 Fire Source Terms (curies)

Nuclide ABD Fire OP Fire FTC Fire BAS Fire Sr-90 l.5E-04 9.lE-04 3.7E-05 2.5E-04 Cs-137 1.8E-03 3.0E-03 4.5E-05 2.8E-03 Pu-238 2.7E-07 3.5E-07 1.5E-07 3.7E-07 Pu-239 l.7E-06 2.2E-06 8.8E-07 2.3E-06 Pu-240 8.2E-07 1.IE-06 4.3E-07 1.lE-06 Pu-241 1.9E-05 2.5E-05 l.0E-05 2.6E-05 Am-241 2.8E-06 3.6E-06 l.5E-06 3.8E-06 2.2 Dose Conversion Factors Federal Guidance Report 11 (FGR-11) [Ref. 4.7] provides exposure to dose conversion factors for inhalation of radionuclides. For some nuclides, FGR-11 reports several sets of dose conversion factors depending on the lung clearance class of the chemical form of the inhaled nuclide. For the sake of conservatism, the chemical form of the nuclide is ignored and the maximum dose conversion values are used. The only exceptions are the plutonium nuclides, which use the dose conversion factors associated with the oxide form ('year' lung clearance classification). This is discussed in Assumption 3.7.

Federal Guidance Report 12 (FGR-12) [Ref. 4.8] provides external exposure dose conversion factors for submersion in air. Note that the following tables include nuclides not presented in Table 1. These additional nuclides are daughter products of the decay performed as part of this analysis. See Section 6.5 for discussion of decay of the source terms. Note that the inhalation dose conversion factors for Ba-137m are presented at zero. This is because the dose contribution ofBa-137m is included in the dose conversion factors for Cs-137 (Ba-137m being a short-lived daughter ofCs-137).

Table 2. FGR-11 Exposure to Dose Conversion Factors for Inhalation (Sv/Bq)

Nuclide Gonad Breast Lung Marrow Bone Thyroid Remainder Effective Sr-90 2.64E-09 2.64E-09 2.86E-06 3.36E-07 7.27E-07 2.64E-09 5.73E-09 3.51E-07 Y-90 9.52E-12 9.52E-12 9.31E-09 2.79E-10 2.78E-10 9.52E-12 3.87E-09 2.28E-09 Cs-137 8.76E-09 7.84E-09 8.82E-09 8.30E-09 7.94E-09 7.93E-09 9.12E-09 8.63E-09 Ba-137m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Th-230 4.08E-07 4.08E-07 3.00E-04 l.73E-04 2.16E-03 4.08E-07 l.05E-06 8.80E-05 Th-231 7.62E-12 3 OOE-12 8.75E-10 7.88E-l l 9.22E-10 l.97E-12 3.91E-IO 2.37E-10 Pa-233 l.29E-10 9.20E-l l l.70E-08 8.21E-10 7.37E-09 5.62E-l l l.48E-09 2.58E-09 U-233 2.54E-08 2.54E-08 3.04E-04 7.12E-07 l.12E-05 2.54E-08 9.40E-07 3.66E-05 U-234 2.50E-08 2.50E-08 2.98E-04 6.98E-07 l.09E-05 2.50E-08 2.50E-08 3.58E-05 U-235 2.37E-08 2.38E-08 2.76E-04 6.58E-07 1.0!E-05 2.37E-08 8.59E-07 3.32E-05 U-236 2.37E-08 2.37E-08 2.82E-04 6.60E-07 l.04E-05 2.37E-08 8.77E-07 3.39E-05 U-237 8.15E-ll 3.39E-l 1 4.70E-09 4.12E-10 4.02E-09 2.62E-11 l.19E-09 9.54E-10 Np-237 2.96E-05 l.69E-08 l.61E-05 2.62E-04 3.27E-03 1.34E-08 2.34E-05 l.46E-04 Pu-238 l.04E-05 4.40E-10 3.20E-04 5.80E-05 7.25E-04 3.86E-10 2.74E-05 7.79E-05 Pu-239 1.20E-05 3.99E-10 3.23E-04 6.57E-05 8.21E-04 3.75-10 3.02E-05 8.33E-05 Pu-240 1.20E-05 4.33E-10 3.23E-04 6.57E-05 8.21E-04 3.76E-10 3.02E-05 8.33E-05 Pu-241 2.76E-07 2.14E-11 3.18E-06 l.43E-06 l.78E-05 9. lSE-12 6.02E-07 l.34E-06 Am-241 3.25E-05 2.67E-09 l.84E-05 l.74E-04 2.l 7E-03 l.60E-09 7.82E-05 l.20E-04

4440-7380-90-017, Revision 3 Page 4 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Tenns Tabl e 3. F GR- 12 Exposure to Dose Convers10n Factors £or A.Ir Sb u mers10n (S v-m :q-s Nuclide Gonad Breast Lung Marrow Bone Thyroid Remainder Effective Skin Sr-90 7.78E-18 9.49E-18 6.44E-18 5.44E-18 2.28E-17 7.33E-18 6.l lE-18 7.53E-18 9.20E-15 Y-90 1.89E-16 2.20E-16 1.77E-16 1.62E-16 4.44E-16 1.87E-16 l.68E-16 l.90E-16 6.24E-14 Cs-137 7.96E-18 9.67E-18 6.68E-18 5.70E-18 2.29E-17 7.55E-18 6.34E-18 7.74E-18 8.63E-15 Ba-137m 2.82E-14 3.22E-14 2.80E-14 2.73E-14 4.63E-14 2.88E-14 2.68E-14 2.88E-14 3.73E-14 Th-230 1.80E-17 2.38E-17 l.43E-17 1.22E-17 5.29E-17 l.63E-17 l.37E-17 l.74E-17 4.SIE-17 Th-231 5.39E-16 6.79E-16 4.35E-16 3.70E-16 l.63E-15 5.00E-16 4.15E-16 5.22E-16 2.52E-15 Pa-233 9.16E-15 l.05E-14 8.88E-15 8.27E-15 2 08E-14 9.21E-15 8.42E-l 5 9.35E-15 l.66E-14 U-233 1.69E-17 2.22E-17 1.35E-17 l.24E-17 4.12E-17 1.55E-17 l.31E-17 l.63E-17 4.57E-17 U-234 8.79E-18 l.44E-17 4.38E-l 8 4.20E-18 l.99E-17 6.69E-18 4.80E-] 8 7.63E-18 4.25E-17 U-235 7 0SE-15 8.I IE-15 6.75E-15 6.ISE-15 l.84E-14 7.05E-15 6.37E-15 7.20E-15 8.64E-15 U-236 6.J0E-18 1.1 0E-17 2. l 8E-18 2.33E-18 1.19E-17 4.19E-18 2.70E-18 5.0lE-18 3.57E-17 U-237 5.90E-15 6.90E-15 5.48E-15 4.82E-15 l.69E-14 5.81E-15 5.15E-15 5.97E-15 9.97E-15 Np-237 1.04E-15 l.26E-15 9.02E-16 7.69E-16 3.20E-15 9.94E-16 8.50E-16 l.03E-15 1.54E-15 Pu-238 6.56E-18 l.27E-17 1.06E-!8 l.68E-18 9.30E-18 4.0IE-18 l.99E-18 4.88E-18 4.09E-17 Pu-239 4.84E-18 7.55E-18 2.65E-l 8 2.67E-18 9.47E-18 3.88E-18 2.86E-18 4.24E-18 1.86E-17 Pu-240 6.36E-18 l.23E-17 1.09E-!8 1.65E-18 9.26E-l 8 3.92E-18 1.96E-18 4.75E-18 3.92E-17 Pu-241 7.19E-20 8.67E-20 6.48E-20 5.63E-20 2.19E-19 6.98E-20 6.09E-20 7.25E-20 1.17E-19 Am-241 8.58E-16 l.07E-15 6.74E-16 5.21E-16 2.87E-15 7.83E-16 6.34E-16 8.18E-16 l.28E-15 2.3 Chi/Q Value TMI-2 calculation #87-008 [Ref. 4.5], Appendix I Dose Calculations, models several offsite releases and identifies 7.67E-04 s/m 3 as the worst case X/Q value for a TMI-2 release.

2.4 Breathing Rate NRC Regulatory Guide 1.183 [Ref. 4.11 ], Alternative Radiological Source Terms for Evaluating Design Basis Accident at Nuclear Power Reactors, provides offsite dose consequence methodology. As part of the guidance, it outlines several assumptions related to dose calculations. It states that breathing rate 3

should be assumed to be 3.5E-04 m /s for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months post-accident.

2.5 Radionuclide Decay Schemes and Decay Constants Pertinent to calculating the decay of the source terms, decay constants and schemes for the nuclides are needed. DOE/TIC-11026 [Ref. 4.6], Radioactive Decay Data Tables, by David C. Kocher provides comprehensive data on the decay of radionuclides. The transuranic radionuclides have long decay chains, transmutating through many isotopes before reaching stability. Note that for the purpose of this calculation, the transuranic decay chains are cut off at points where the concentrations of the daughter products are judged as insignificant. For example, the decay chain of Pu-238 is ended at Th-230 even though Th-230 is not stable, but the concentration ofTh-230 resulting from decay of Pu-238 is such as to deem it insignificant to the dose calculation.

T abl e 4 R a d.10nucl"d 1 e D ecay Sh c emes an dD ecay C onstants Parent First Dau~ hter Second Daughter I Third Daughter Nuclide Halflife Mode Yield Nuclide Halflife Mode I Yield Nuclide I Halflife I Mode I Yield I Nuclide I Halflife Sr-90 28.6y Beta- I Y-90 64.1 h Beta- I 1 Zr-90 I Stable I Beta- 0.946 Ba-137m 2.522 m IT I 1 Ba-137 I Stable I Cs-137 30.17y Beta- 0.054 Ba-137 Stable Pu-238 87.75 v Alpha 1 U-234 2.445E5 y Alpha I 1 Th-230 1 I 7.7E4y I Pu-239 24131 y Alpha I U-235 1 7.038E8 y Pu-240 6569 y Aloha I U-236 1 2.3415E7 v Beta- 0.999976 Am-241 See below Pu-241 14.4 y Alpha 2.45E-05 U-237 6.75 d Beta - I I Np-237 I See below I Am-241 432.2 y Alpha I No-237 2.14E6v Aloha I I Pa-233 I 27.0d I Beta- I I I U-233 1 I l.592E5 y Note 1: Decay chain ended at this low concentrations/long-lived nuclide

4440-7380-90-017, Revision 3 Page 5 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 2.6 Plume Release Time For Case 2 (See Section 6.3), the activity made airborne by the fire is slowly released to the environment over a period of 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months [Ref. 4.12].

3 .0 ASSUMPTIONS The TMI-2 Fire Protection Program Evaluation, 990-3017 [Ref. 4.10], discusses the fire analysis in detail, including assumptions associated with the fire dose calculation. Several of the pertinent assumptions are presented here.

3. l Deterministic Nature of Fires All fires are deterministic and non-mechanistic. All combustibles are consumed and all equipment fails except metal enclosures. It is assumed that no water is available to affect the fire in the reactor vessel, fuel transfer canal, and the fuel pool.

3 .2 Activity Released as Particulate It is assumed that all activity released from the fire is particulate in nature. In the unlikely event that any elemental forms are vaporized, the activity would likely attach to airborne particulates.

3.3 No Credit for Plateout No credit is taken for plateout of activity in the fire scenarios, maximizing the activity available for atmospheric release.

3.4 HEPA Efficiency It is assumed that the HEPA filters of the reactor building purge and reactor building breather are 99%

efficient.

3.5 Automatic Isolation of Reactor Building Breather Line The automatic isolation valve in the reactor building breather line upstream of the HEPA filter closes upon the receipt of a containment pressure increase of 0 .25 psi.

3 .6 Particle Size of Source Term Particulates It is assumed that all particulate released consists of particles less than 10 µm, maximizing the dose consequence of inhalation.

3.7 Chemical Form of Plutonium It is assumed that all plutonium released by the postulated fire is in the form of an oxide chemical compound. Plutonium is generated in the reactor fuel by transmutation of uranium, which exists in the UO2 form. There is no indication, when this transmutation occurs, that plutonium will be freed from the oxide structure. Thus it is deemed reasonable to assume that all plutonium present in the reactor building is in the form of an oxide chemical compound. This assumption is supported by chemical analysis of core debris recovered from the TMI-2 reactor [Table 24 of Ref. 4.14].

3.8 Case 1 Assumptions It is assumed that the fire occurs while the reactor building purge system is operating. It is assumed that the activity released by the fire is released instantaneously (1 second) to the environment due to the high flow rate of the purge system. These assumptions are conservative because they maximize the rate of release of activity from the fire.

4440-7380-90-017, Revision 3 Page 6 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 3 .9 Case 2 Assumptions The reactor building is assumed to be isolated and at a slight negative pressure for the Case 2 evaluation.

It is assumed that there is no deposition inside the reactor building after the fire. This is conservative because it maximizes the activity available to be released to the environment. It is assumed that activity entrained by the fire is released to the environment sometime after the fire, when the containment is eventually purged. Thus all activity released by the fire is subsequently released to the environment over a longer (than Case 1) period of time, amounting to 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

3.10 Case 3 Assumptions It is assumed that the fire occurs while the reactor building is under passive ventilation.

4.0 REFERENCES

1. 4440-7380-90-017, Revision 0, PDMS SAR Section 8.2.5 Fire Analysis Source Terms

2. 4440-7380-90-017, Revision 2, PDMS SAR Section 8.2.5 Fire Analysis Source Terms (Attachment A)

3. GPU Nuclear Memorandum C312-92-1045, Dose Calculations

4. GPU Nuclear Memorandum C312-93-1015, TMI-2 RB Surface Contamination Activity (Attachment C)

5. #87-008, Appendix I Dose Calculations, GPU Nuclear, 1988

6. Kocher, D.C., DOE/TIC-11026, Radioactive Decay Data Tables, 1981

7. Federal Guidance Report No. 11: Limiting Values Of Radionuclide Intake And Air Concentration And Dose Conversion Factors For Inhalation, Submersion, And Ingestion, US EPA, 1988

8. Federal Guidance Report No. 12: External Exposure to Radionuclides in Air, Water, and Soil, US EPA, 1993

9. TMI-2 Post-Defueling Monitored Storage Safety Analysis Report, Update 12

10. 990-3017, Revision 012, TMI-2 Fire Protection Program Evaluation

11. US NRC Regulator Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors

12. Transmittal of Design Information 5971-2019-002, TMI-2 Reactor Building Fire Dose Calculation Design Inputs (Attachment B)

13. Lamarsh, J.R., Baratta, A.J., Introduction to Nuclear Engineering, 3rd Edition

14. GEND-INF-075-PT-l, TMI-2 Core Debris Grab Samples -Examination and Analysis Part 1

15. Title 10 Code of Federal Regulations Part 20, Standards for Protection Against Radiation

16. Title 10 Code of Federal Regulations Part 100, Reactor Site Criteria

17. US NRC NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: L WR Edition

18. EPA-400/R-17/001, PAG Manual: Protective Action Guides and Planning Guidance for Radiological Incidents, US EPA, 2017

19. US NRC Regulatory Guidance 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I

20. Title 10 Code of Federal Regulations Part 50, Domestic Licensing of Production and Utilization Facilities 5.0 IDENTIFICATION OF COMPUTER PROGRAMS Microsoft Excel 2010 was used to perform numerical analysis in this calculation.

4440-7380-90-017, Revision 3 Page 7 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 6.0 METHOD OF ANALYSIS 6.1 PDMS Unanticipated Events Unanticipated radiological releases could occur from unanticipated events arising from the condition or activities postulated during PDMS. One such event postulated is a fire in the reactor building, which could entrain radioactive particulates and release them to the atmosphere through the various ventilation paths of the reactor building. This analysis follows methodology guidance presented in Regulatory Guide 1.109 [Ref. 4.19].

For the purpose of this analysis, fires are postulated in four distinct reactor building areas. Each area has a unique combustible loading, radionuclide inventory, and release pathway. This results in activity releases unique to each area. The four areas are: The operating deck (OP), A & B D-Rings (ABD), Fuel Transfer Canal (FTC), and basement area (BAS). Dose analysis is performed for each area.

Conditions in the reactor building can affect the nature of the release of activity due to a fire. For the purpose of this analysis, the three fire scenarios are as follows.

6.2 Case 1: Reactor Building Purge System Operating For Case 1, it is assumed that the fire occurs while the reactor building purge is operating. The purge system operates at its normal flowrate for the duration of the fire. Due to the relatively high flowrate out of the contaimnent, it is assumed that activity released by the fire in the reactor building is released instantaneously (1 second) to the atmosphere, constituting a puff release. See Assumption 3.8. Due to the instantaneous nature of the Case 1 release, only acute inhalation dose is considered.

Offsite dose is calculated by first determining the activity at the offsite receptor. This is done by adjusting the activity released by the fire using the X/Q value. For external submersion dose, the adjusted activity is multiplied by the appropriate dose conversion factor to yield an external dose. For internal inhalation dose, the adjusted activity is multiplied by the breathing rate and dose conversion factor to yield an internal dose. Total dose is determined by summing the internal and external dose contributions over all nuclides.

(Ai[Ci] ~ [~ 3 ] DCFair,i + Ai[Ci]BR [~ ~

3 3 Dose [mrem] = Li [mr;:~m ] ] [~3 ] DCFinhale,i [m~:m]) t

Where, Dose = Dose to given organ or effective dose summed for all nuclides, mrem A; = Activity release rate of nuclide i, Ci/s X

Q

= Chi over Q value for receptor location, s/m3 DCFair,i = Dose conversion factor for air submersion for nuclide i, mrem-m 3/Ci-s DCF;,,l,a/e,i = Dose conversion factor for inhalation for nuclide i, mrem /Ci t = Release time (1 second)

BR = Breathing rate, m 3/s 6.3 Case 2: Reactor Building at Negative Pressure For Case 2, it is assumed that the reactor building is isolated and is being held at a slight negative pressure. The postulated fire releases a portion of the radionuclide inventory to the reactor building atmosphere. Since the reactor building is isolated, the released activity diffuses through the reactor building atmosphere. It is assumed that sometime after the fire the reactor building is purged and the diffused airborne activity is released to the environment. It is assumed that there is no deposition inside the reactor building after the fire and all activity released by the fire is subsequently released to the environment over a longer (than Case 1) period of time, amounting to 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months . This slow release constitutes a plume release. See Assumption 3.9. This scenario considers multiple exposure pathways as dictated by Appendix I of 10 CFR 50 [Ref. 4.20].

4440-7380-90-017, Revision 3 Page 8 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Revision 2 of this analysis [Ref. 4.2] shows that the Case 1 dose bounds the Case 2 dose to a significant degree (Case I: 13.5 mrem to bone, Case 2: 3.0 mrem to bone). The difference in dose is the result of the characteristic difference between Case 1 and Case 2, specifically the instantaneous release of Case 1 compared to the slow release of Case 2. None of the changes implemented as part of this revision of the analysis impact the instantaneous nature of Case 1. The characteristic differences between Case 1 and Case 2 are maintained and thus Case 1 continues to bound Case 2. Because the Case I analysis bounds the Case 2 fire, no new dose analysis is performed for Case 2.

6.4 Case 3: Reactor Building under Passive Ventilation For Case 3, it is assumed that the postulated fire occurs while the reactor building is under passive ventilation. See Assumption 3.10. For this case the fire can be either small or large. If small, the activity released by the fire would be vented to the environment through the filtered breather, driven by the pressure differential generated by the fire itself. However, given the small size of the fire, the quantity of activity released to the environment would be less than that released in Case 1 through the reactor building purge HEPA filters. Thus the dose consequences of a small fire Case 3 are bounded by Case 1.

If large, the fire would create a pressure differential sufficiently high (greater than 0.25 psi, see Assumption 3.5) to actuate the breather isolation valve to close and effectively seal off the reactor building. Although the reactor building is not air-tight, the amount of activity released to the environment would be significantly less than the amount of activity released by the fire postulated in Case I. Although no credit is taken for removal of airborne activity by the HEPA filters, the amount of activity released to the environment in a Case 3 fire is less than the filtered amount for the Case 1 fire, thus the dose consequences of a Case 3 large fire are bounded by Case 1.

Because in all scenarios Case 1 bounds Case 3 fires, no new dose analysis is performed for Case 3.

6.5 Source Term Modification The objectives of this revision of the calculation include revising the source terms of the postulated fires.

The Revision 2 source terms are presented in Table 1. For this revision, the source terms are revised to 1) include additional identified contamination activity and 2) consider 26 years ofradiodecay.

Memorandum C312-93-1015 [Ref. 4.4], TMI-2 RB Surface Contamination Activity, discusses the impact of additional surface contamination surveyed in the reactor building. The memo goes on to show that the impact of this additional activity on the offsite fire doses is insignificant. However, this additional surface activity is added to the source term in this analysis for completeness. The memo states that additional Cs-137 and Sr-90 found in the basement (BAS) of the reactor building amounted to a 0.7% (Cs-137) and 9.7% (Sr-90) increase in activity, respectively. For the purpose of this analysis, these values are conservatively increased to 1% and 10%, respectively, and applied to the Cs-137 and Sr-90 release activities for the BAS fire.

Since 26 years have passed since Revision 2 of this calculation was issued, the radioactive sources available to be released by a fire in the reactor building have decayed. This decay can be calculated using radioactive decay equations from Lamarsh [Ref. 4.13]. When assessing the decay of a radionuclide there are three categories to consider:

1. Radionuclides present at the start that decay, producing daughter products, but aren't themselves daughter products of any radionuclides initially present or created. These radionuclides are subject to simple decay. Example: Sr-90

2. Radionuclides not present at the start, but are daughter products of parent radionuclides that decay.

These radionuclides are subject to complex daughter decay. Example: U-234

4440-7380-90-017, Revision 3 Page 9 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Te1ms

3. Radionuclides present at the start that decay and are themselves also daughter products of any radionuclides initially present or created. These radionuclides are subject to complex daughter decay.

Example: Am-241 For simple decay (decay type 1) the equation used is from Lamarsh [Equation 2.25 of Ref. 4.13]:

a(t) = a 0 e-,lt

Where, a.(t) = Amount of an isotope at time t, activity or equivalently scaled unit a.o = Amount of an isotope at time t = 0, activity or equivalently scaled unit A = Decay constant of the isotope, year" 1

= Decay time, years For complex daughter decay (decay type 2 and 3) an equation from Lamarsh [Equation 2.33 of Ref. 4.13]

is modified to account for differing yields:

- -,ldt + apoYild ( -il t -ildt) ad - ado e ild - ilp e P - e

Where, a., = Amount of a daughter isotope at time t, activity or equivalently scaled unit a.Jo = Amount of a daughter isotope at time t = 0, activity or equivalently scaled unit a.po = Amount of a parent isotope at time t = 0, activity or equivalently scaled unit y = Fractional branching ratio (yield) by which the parent isotope decays into the daughter isotope Ad = Decay constant of the daughter isotope, year" 1 A, = Decay constant of the parent isotope, year- 1 t = Decay time, years The first term in the complex daughter equation is simple decay of any initially present daughter activity.

If the radionuclide in question is not present initially (decay type 2), this term is zero. If a radionuclide is the daughter of more than one parent (e.g., Np-237), the second te1m of the equation is replicated for each subsequent parent. Note that the decay constant is the natural log of two over the half-life of the radionuclide.

7.0 NUMERIC ANALYSIS 7.1 Source Term Determination The additional surface contamination identified in Reference 4.4 is added to the release activity for the BAS fire by the appropriate percentage.

Table 5. Adjusted BAS Fire Release Activity (curies)

Nuclide BAS Activity Additional New BAS Activity Sr-90 2.SE-04 10% 2.75E-04 Cs-137 2.8E-03 1% 2.83E-03 Pu-238 3.7E-07 - 3.7E-07 Pu-239 2.3E-06 - 2.3E-06 Pu-240 1. lE-06 - l.lE-06 Pu-241 2.6E-05 - 2.6E-05 Am-241 3.8E-06 - 3.8E-06 The fire source terms are decayed per the methodology discussed in Section 6.5. Each fire scenario source terms is decayed for 26 years. Doing so reduces the activities of the initially present radionuclides, but also generates radioactive daughter products that may contribute to the offsite dose in case of a fire. From the decayed release activities, two source terms are generated for each fire scenario. The first is used in

4440-7380-90-017, Revision 3 Page 10 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Case 1, dividing the activities by one second to simulate an instantaneous puff release. The second is used in Case 2, dividing the activities by 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months to simulate the plume release.

Table 6. OP Fire Decayed Source Terms Radioactive Decav Puff Release Plume Release Decay Initial Decayed Release Decayed Release Decayed Nuclide Time Activitv Activitv Time Source Term Time Source Term

[yearl [Cil [Cil fsl [Ci/sl [houri [Ci/sl Sr-90 26 9.I0E-04 4.85E-04 I 4.85E-04 14 9.61E-09 Y-90 26 - 4.85E-04 I 4.85E-04 14 9.62E-09 Cs-137 26 3.00E-03 l.65E-03 I l.65E-03 14 3.28E-03 Ba-137m 26 - 1.56E-03 1 1.56E-03 14 3. I0E-08 Th-230 26 - 5.46E-15 I 5.46E-15 14 l.08E-19 Th-231 26 - 5.63E-14 I 5.63E-14 14 1.12E-18 Pa-233 26 - 2.97E-l l I 2.97E-11 14 5.89E-16 U-233 26 - l.38E-17 I l.38E-l 7 14 2.74E-22 U-234 26 - 2.33E-l 1 1 2.33E-l l 14 4.63E-16 U-235 26 - 5.63E-14 1 5.63E-14 14 1.12E-l 8 U-236 26 - 8.45E-13 1 8.45E-13 14 l.68E-17 U-237 26 - 1.75E-10 I 1.75E-I0 14 3.48E-15 No-237 26 - 2.97E-l l I 2.97E-11 14 5.89E-16 Pu-238 26 3.S0E-07 2.85E-07 1 2.85E-07 14 5.66E-12 Pu-239 26 2.20E-06 2.20E-06 1 2.20E-06 14 4.36E-l l Pu-240 26 l.l0E-06 1.I0E-06 1 1.I0E-06 14 2.lSE-11 Pu-241 26 2.50E-05 7.15E-06 I 7.15E-06 14 1.42E-10 Am-241 26 3.60E-06 4.03E-06 I 4.03E-06 14 8.00E-11 T abl e 7 BAS p*Ire D ecave dS ource T erms Radioactive Decav Puff Release Plume Release Decay Initial Decayed Release Decayed Release Decayed Nuclide Time Activitv Activity Time Source Term Time Source Term fvearl [Cil [Cil fsl rci/sf fhourl rci/sl Sr-90 26 2.75E-04 l.46E-04 I l.46E-04 14 2.91E-09 Y-90 26 - 1.46E-04 1 1.46E-04 14 2.91E-09 Cs-137 26 2.83E-03 l.56E-03 1 1.56E-03 14 3.09E-08 Ba-137m 26 - l.47E-03 1 1.47E-03 14 2.92E-08 Th-230 26 - 5.77E-15 I 5.77E-15 14 1.14E-19 Th-231 26 - 5.89E-14 1 5.89E-14 14 1.17E-18 Pa-233 26 - 3.13E-ll 1 3.13E-l l 14 6.22E-16 U-233 26 - 1.46E-17 1 1.46E-17 14 2.89E-22 U-234 26 - 2.47E-l 1 1 2.47E-11 14 4.89E-16 U-235 26 - 5.89E-14 1 5.89E-14 14 1.17E-18 U-236 26 - 8.45E-13 1 8.45E-13 14 1.68E-17 U-237 26 - l.82E-10 1 1.82E-10 14 3.62E-15 No-237 26 - 3.13E-l l 1 3.13E-l l 14 6.22E-16 Pu-238 26 3.70E-07 3.0IE-07 1 3.0lE-07 14 5.98E-12 Pu-239 26 2.30E-06 2.30E-06 1 2.30E-06 14 4.56E-l l Pu-240 26 1.I0E-06 1.I0E-06 1 1.l0E-06 14 2.18E-l l Pu-241 26 2.60E-05 7.44E-06 1 7.44E-06 14 l.48E-10 Am-241 26 3.80E-06 4.25E-06 I 4.25E-06 14 8.43E-l 1

4440-7380-90-017, Revision 3 Page 11 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Table 8. ABD Fire Decayed Source Terms Radioactive Decay Puff Release Plume Release Decay Initial Decayed Release Decayed Release Decayed Nuclide Time Activitv Activitv Time Source Term Time Source Term rvear] fCil [Cil [sl fCi/sl [hourl fCi/s]

Sr-90 26 l.S0E-04 7.99E-05 I 7.99E-05 14 l.58E-09 Y-90 26 - 7.99E-05 I 7.99E-05 14 l.59E-09 Cs-137 26 l.S0E-03 9.90E-04 1 9.90E-04 14 l.97E-08 Ba-137m 26 - 9.37E-04 I 9.37E-04 14 l.86E-08 Th-230 26 - 4.21E-15 1 4.21E-15 14 8.35E-20 Th-231 26 - 4.35E-14 I 4.35E-14 14 8.63E-19 Pa-233 26 - 2.31E-l l I 2.31E-I I 14 4.58E-16 U-233 26 - l.07E-17 I l.07E-17 14 2. 13E-22 U-234 26 - l.80E-ll I l.80E-l l 14 3.57E-16 U-235 26 - 4.35E-14 I 4.35E-14 14 8.63E-l 9 U-236 26 - 6.30E-13 1 6.30E-13 14 l.25E-17 U-237 26 - l.33E-10 1 1.33E-I0 14 2.65E-15 No-237 26 - 2.31E-l l 1 2.31E-l I 14 4.58E-16 Pu-238 26 2.70E-07 2.20E-07 1 2.20E-07 14 4.36E-12 Pu-239 26 l.70E-06 l.70E-06 1 1.70E-06 14 3.37E-l l Pu-240 26 8.20E-07 8. 18E-07 1 8.18E-07 14 l.62E-l l Pu-241 26 l.90E-05 5.44E-06 1 5.44E-06 14 1.08E-10 Am-241 26 2.80E-06 3.13E-06 1 3. 13E-06 14 6.20E-l 1 Tabl e 9 FTC F'ire D ecave dS ource T erms Radioactive Decay Puff Release Plume Release Decay Initial Decayed Release Decayed Release Decayed Nuclide Time Activitv Activitv Time Source Term Time Source Term

[vearl [Cil fCil fsl fCi/sl fhourl fCi/sl Sr-90 26 3.70E-05 l.97E-05 1 1.97E-05 14 3.91E-10 Y-90 26 - l.97E-05 I l.97E-05 14 3.91E-I0 Cs-137 26 4.S0E-05 2.48E-05 1 2.48E-05 14 4.91E-10 Ba-137m 26 - 2.34E-05 1 2.34E-05 14 4.65E-10 Th-230 26 - 2.34E-15 1 2.34E-15 14 4.64E-20 Th-231 26 - 2.25E-14 1 2.25E-14 14 4.47E-19 Pa-233 26 - l.24E-l l 1 l.24E-I I 14 2.45E-16 U-233 26 - 5.75E-18 1 5.75E-18 14 1.14E-22 U-234 26 - 9.99E-12 I 9.99E-12 14 1.98E-16 U-235 26 - 2.25E-14 1 2.25E-14 14 4.47E-19 U-236 26 - 3.31E-13 1 3.31E-13 14 6.56E-18 U-237 26 - 7.02E-l l 1 7.02E-11 14 l.39E-15 No-237 26 - l.24E-l 1 1 l.24E-11 14 2.45E-16 Pu-238 26 l.S0E-07 1.22E-07 1 1.22E-07 14 2.42E-12 Pu-239 26 8.S0E-07 8.79E-07 1 8.79E-07 14 !.74E-11 Pu-240 26 4.30E-07 4.29E-07 1 4.29E-07 14 8.SIE-12 Pu-241 26 1.00E-05 2.86E-06 1 2.86E-06 14 5.68E-1 l Am-241 26 1.S0E-06 l.67E-06 I l.67E-06 14 3.31E-11 In general, nuclides initially present see some degree of reduction in activity due to the decay. Note that the activities for Pu-239 and Pu-240 don't decrease significantly due to their relatively long half-lives.

Significant to note, the activity of Am-241 increases over the 26 years of decay due to it being the daughter product of Pu-241 decay. This is especially significant because Am-241 is a relatively large inhalation dose contributor.

7.2 Case 1 Analysis The puff dose source terms from Section 7 .1 are used to calculate offsite doses for the four reactor building areas. Dose conversion factors from Section 2.2 are used to convert offsite receptor exposure to dose. The dose conversion factors are presented in SI units (e.g., Sv/Bq for inhalation). These units are converted to mrem (1.00E+0S mrem per Sv) and Ci (2.70E-l 1 Ci per Bq) for the purpose of this analysis.

Offsite receptor exposure is determined by the X/Q value (7 .67E-04 s/m3) with the breathing rate (3 .50E-04 m 3/s) factored in for inhalation dose.

4440-7380-90-017, Revision 3 Page 12ofl7 PDMS SAR Seclion 8.2.5 Fire Analysis Source Terms Table IO. TMI-2 OP Fire Case I Offsite Dose ConseQuences External Air Submersion Dose Internal Inhalation Dose Totals Release Thyroid Lung Thyroid Maximum Organ Nuclide Gonad Breast Lung Marrow Bone Rmnder Effective Skin Gonad Breast Morrow Bone Rlnnder Effective Effective TEDE Bone Total Dose ICi/sl rmreml rmreml rmreml rmreml rmreml rmreml rmreml rmreml rmrcml rmrcml rmreml rmrcml rmreml rmreml rmreml rmreml rmreml rmreml rmreml Sr-90 4.85E-04 1.0)E-08 1.31E-08 8.87E-09 7.49E-09 3.14E-08 1.01E-08 8.41E-09 1.D4E-DB 1.27E-05 1.27E-03 1.27E-D3 1.3BE<OD 1.62E-D1 3.5DE-01 1.27E-03 2.76E-D3 1.69E-01 1.69E-01 3.5DE-01 Y-90 4.85E-04 2.60E-07 3.03E-07 2.44E-07 2.23E-07 6.11E-07 2.57E-07 2.31E-07 2.62E-07 8.59E-05 4.59E-D6 4.59E-06 4.49E-03 1.34E-04 1.34E-04 4.59E-06 1.BlE-03 1.1DE-03 1.1DE-03 1.35E-04 Cs-137 1.65E-03 3.73E-08 4.53E-08 3.13E-08 2.67E-08 1.DlE-07 3.54E-08 2.97E-08 3.63E-08 4.05E-05 1.44E-D2 1.29E-02 1.45E-02 1.36E-D2 1.3DE-02 1.3DE-02 1.5DE-02 1.42E-02 1.42E-02 1.30E-02 Ba-137m 1.56E-03 1.25E-04 1.43E-04 1.24E-04 1.21E-04 2.05E-04 1.28E-04 1.19E-04 1.28E-04 1.65E-04 0.OOE<OO 0.OOE<OD D.D0E<OO D.DDE<OO D.OOE<O0 D.OOE<OD 0.OOE<OD D.D0E<OD 1.2BE-04 2.DSE-04 Th-230 5.46E-15 2.79E-19 3.69E-19 2.22E-19 1.B9E-19 B.2DE-19 2.53E-19 2.12E-19 2.lDE-19 6.99E-19 2.21E-12 2.21E-12 1.63E-09 9.39E-10 1.17E-OB 2.21E-12 5.lDE-12 4.77E-10 4.77E-1D 1.17E-OB Th-231 5.63E-14 B.62E-17 1.09E-16 6.96E-17 5.92E-17 2.61E-16 8.00E-17 6.64E-17 8.35E-17 4.D3E-16 4.27E-16 1.68E-16 4.9DE-14 4.41E-15 5.16E-14 1.1DE-16 2.19E-14 1.33E-14 1.34E-14 5.19E-14 Pa-233 2.97E-11 7.73E-13 8.86E-13 7.49E-13 6.98E-13 1.75E-12 7.77E-13 7.1DE-13 7.89E-13 1.40E-12 3.81E-12 2.72E-12 5.02E-1D 2.42E-11 2.1BE-10 1.66E-12 4.37E-11 7.62E-11 7.7DE-11 2.19E-10 U-233 1.3BE-17 6.62E-22 8.lDE-22 5.29E-22 4.86E-22 1.61E-21 6.07E-22 5.13E-22 6.39E-22 1.79E-21 3.48E-16 3.48E-16 4.17E-12 9.77E-15 1.54E-13 3.48E-16 1.29E-14 5.02E-13 5.02E-13 1.54E-13 U-234 2.33E-11 5.82E-16 9.54E-16 2.9DE-16 2.78E-16 1.32E-15 4.43E-16 3.18E-16 5.05E-16 2.82E-15 5.BDE-10 5.B0E-10 6.91E-06 1.62E-08 2.53E-07 5.B0E-10 2.15E-08 8.3DE-07 8.30E-07 2.53E-07 U-235 5.63E-14 1.13E-15 1.3DE-15 1.DBE-15 9.84E-16 2.94E-15 1.13E-15 1.02E-15 1.15E-15 1.38E-15 1.33E-12 1.33E-12 1.53E-08 3.68E-11 5.65E-10 1.33E-12 4.81E-11 1.86E-09 1.86E-09 5.66E-10 U-236 B.45E-13 1.47E-17 2.64E-17 5.24E-18 5.60E-18 2.86E-17 1.01E-17 6.4BE-18 1.2DE-17 8.57E-17 1.99E-11 1.99E-11 2.37E-07 5.55E-10 8.74E-09 1.99E-11 7.37E-10 2.B5E-DB 2.85E-OB 8.74E-09 U-237 1.75E-10 2.94E-12 3.44E-12 2.73E-12 2.4DE-12 8.42E-12 2.90E-12 2.57E-12 2.98E-12 4.97E-12 1.42E-11 5.91E-12 8.2DE-10 7.19E-11 7.01E-10 4.57E-12 2.DBE-10 1.66E-10 1.69E-10 7.1DE-10 Np-237 2.97E-11 8.77E-14 1.D6E-13 7.61E-14 6.49E-14 2.7DE-13 8.38E-14 7.17E-14 8.69E-14 1.30E-13 8.74E-07 4.99E-10 4.75E-07 7.74E-06 9.65E-05 3.96E-10 6.91E-07 4.31E-06 4.31E-06 9.65E-05 Pu-238 2.85E-07 5.31E-12 1.03E-11 B.5BE-13 1.36E-12 7.53E-12 3.25E-12 1.61E-12 3.95E-12 3.31E-11 2.95E-03 1.25E-07 9.07E-02 1.64E-02 2.05E-01 1.09E-07 7.76E-03 2.21E-02 2.21E-02 2.05E-01 Pu-239 2.2DE-06 3.D2E-11 4.71E-11 1.65E-11 1.67E-11 5.91E-11 2.42E-11 1.79E-11 2.65E-11 1.16E-10 2.62E-02 8.72E-07 7.06E-01 1.44E-01 1.79E<OD 8.20E-07 6.60E-02 1.82E-01 1.82E-01 1.79E<OD Pu-240 1.1DE-06 1.98E-11 3.83E-11 3.40E-12 5.14E-12 2.89E-11 1.22E-11 6.11E-12 1.48E-11 1.22E-10 1.31E-02 4.72E-07 3.52E-01 7.17E-02 8.95E-01 4.10E-07 329E-02 9.09E-02 9.09E-02 8.95E-01 Pu-241 7.15E-06 1.46E-12 1.76E-12 1.32E-12 1.14E-12 4.45E-12 1.42E-12 1.24E-12 1.47E-12 2.38E-12 1.96E-03 1.52E-07 2.26E-02 1.02E-02 1.27E-01 6.51E-OB 4.28E-03 9.53E-D3 9.53E-03 1.27E-01 Am-241 4.03E-06 9.83E-09 1.23E-08 7.72E-09 5.97E-09 3.29E-08 8.97E-09 7.26E-09 9.37E-09 1.47E-08 1.3DE-01 1.DlE-05 7.38E-02 6.98E-01 8.70E<OD 6.42E-06 3.14E-01 4.81E-01 4.81E-01 8.70E<OO Totals 1.25E-04 1.43E-04 1.25E-04 1.21E-04 2.06E-04 1.28E-04 1.19E-04 1.28E-04 3.0SE-04 1.9DE-01 1.42E-02 2.64E<OO 1.12E<OO 1.21E<01 1.43E-02 4.44E-01 9.70E-01 9.70E-D1 1.21E+01

4440-7380-90-0I 7, Revision 3 Page 13 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Tcnns Thi a e 11 TMl2BASF'ue Case JOIE' site Dose Conseauences External Air Submersion Dose Inlemal Inhalation Dose Tolnls Release Maximum Organ Nuclide Gonad Breast Lung Marrow Bone Thyroid Rmndcr Effccti\'e Skin Gonad Breast Lung Marrow Bone Thyroid Rmnder Effccti,*e Eficcti\'e TEDE Bone Total Dose rCi/sI fmreml lmrcml fmrcml fmrcml fmrcml fmrcml fmrcml fmrcml fmreml lrureml fmreml [mrcml fmreml lmreml lmreml fmreml lmreml fmreml lmreml Sr-90 1.46E-04 3.24E-09 3.95E-09 2 6BE-09 2.26E-09 9.48E-09 3.05E-09 2.54E-09 3.13E-09 3.83E-06 3.84E-04 3.84E-04 4.16E-01 4.89E-02 1.06E-01 3.84E-04 B.34E-04 5.11E-02 5.11E-02 1.06E-01 Y-90 1.46E-04 7.86E-OB 9.15E-08 7.3/E-08 6.74E-08 1.85E-07 7.IBE-08 6.99E-OB 7.91E-OB 2.60E-05 1.39E-06 1.39E-06 1.36E-03 4.06E-05 4.05E-05 1.39E-06 5.64E-04 3.32E-04 3.32E-04 4.0IE-05 Cs-137 1.56E-03 3.52E-08 4.27E-08 2.95E-08 2.52E-08 1.01E-07 3.34E-08 2.B0E-08 3.42E-08 3.82E-05 1.36E-02 1.21E-02 1.36E-02 1.28E-02 1.23E-02 1.23E-02 1.41E-02 1.34E-02 1.34E-02 1.23E-02 Ba-137m 1.47E-03 1.18E-04 1.35E-04 1.17E-04 1.14E-04 1.94E-04 1.20E-04 1.12E-04 1.20E-04 1.56E-04 0.OOE->-00 0.00E->00 0.00E->-00 0.00E->00 0.OOE->00 0.00E->00 0.00E->-00 0.OOE->00 1.20E-04 1.94E-04 Th-230 5.77E-15 2.95E-19 3.90E-19 2.34E-19 2.00E-19 8.67E-19 2.6/E-19 2.25E-19 2.85E-19 7.39E-19 2.34E-12 2.34E-12 1.72E-09 9.92E-10 1.24E-08 2.34E-12 6.02E-12 5.05E-10 5.05E-10 1.24E-08 Th-231 5.89E-14 9.01E-17 1.14E-16 7.28E-17 6.19E-17 2.73E-16 8.36E-17 6.94E-17 8.73E-17 4.21E-16 4.46E-16 1.76E-16 5.12E-14 4.61E-15 5.40E-14 1.15E-16 2.29E-14 1.39E-14 1.40E-14 5.42E-14 Pa-233 3.13E-11 8.16E-13 9.35E-13 7.91E-13 7.36E-13 1.85E-12 8.20E-13 7.50E-13 8.32E-13 1.48E-12 4.02E-12 2.BIE-12 5.30E-10 2.56E-11 2.30E-10 1.75E-12 4.61E-11 8.04E-11 8.12E-11 2.32E-10 U-233 1.46E-17 6.99E-22 9.18E-22 5.5BE-22 5.13E-22 1.I0E-21 6.41E-22 5.42E-22 6.74E-22 1.89E-21 3.6BE-16 3.68E-16 4.40E-12 1.03E-14 1.62E-13 3.6BE-16 1.36E-14 5.30E-13 5.30E-13 1.62E-13 U-234 2.4/E-11 6.16E-16 1.01E-15 3.0IE-16 2.94E-16 1.39E-15 4.69E-16 3.36E-16 5.34E-16 2.9BE-15 6.13E-10 6.13E-10 7.30E-06 1.71E-08 2.67E-07 6.13E-10 2.2/E-OB 8.IBE-07 8.IBE-07 2.6/E-07 U-235 5.89E-14 1.18E-15 1.36E-15 1.13E-15 1.03E-15 3.0BE-15 1.18E-15 1.0IE-15 1.20E-15 1.44E-15 1.39E-12 1.39E-12 1.60E-0B 3.85E-11 5.91E-10 1.39E-12 5.03E-11 1.94E-09 1.94E-09 5.91E-10 U-236 8.45E-13 1.4/E-17 2.64E-17 5.24E-18 5.60E-18 2.86E-17 1.01E-17 6.48E-18 1.20E-17 8.5/E-17 1.99E-11 1.99E-11 2.3/E-07 5.55E-10 8.74E-09 1.99E-11 7.3/E-10 2.85E-08 2.85E-08 8.74E-09 U-237 1.82E-10 3.06E-12 3.58E-12 2.B4E-12 2.50E-12 8.76E-12 3.01E-12 2.6/E-12 3.09E-12 5.17E-12 1.48E-11 6.15E-12 8.53E-10 7.4/E-11 7.29E-10 4.75E-12 2.16E-10 1.73E-10 1.76E-10 7.3BE-10 Np-237 3.13E-11 9.26E-14 1.12E-13 8.03E-14 6.85E-14 2.85E-13 8.85E-14 7.SIE-14 9.17E-14 1.3/E-13 9.22E-07 5.27E-10 5.02E-07 8.16E-06 1.02E-04 4.1BE-10 7.29E-07 4.55E-06 4.55E-06 1.02E-04 Pu-238 3.01E-07 5.61E-12 1.09E-11 9.0IE-13 1.44E-12 7.96E-12 3.43E-12 1.I0E-12 4.18E-12 3.50E-11 3.12E-03 1.32E-07 9.59E-02 1.74E-02 2.1/E-01 1.16E-07 B.21E-03 2.33E-02 2.33E-02 2.17E-01 Pu-239 2.30E-06 3.16E-11 4.93E-11 1.73E-11 1.74E-11 6.18E-11 2.53E-11 1.B7E-11 2.77E-11 1.21E-10 2.74E-02 9.12E-07 7.38E-01 1.50E-01 1.BBE->00 8.SIE-07 6.90E-02 1.90E-01 1.90E-01 1.BBE->00 Pu-240 1.10E-06 1.98E-11 3.83E-11 3.40E-12 5.14E-12 2.89E-11 1.22E-11 6.11E-12 1.4BE-11 1.22E-10 1.31E-02 4.72E-07 3.52E-01 7.17E-02 B.95E-01 4.10E-07 3.29E-02 9.09E-02 9.09E-02 8.95E-01 Pu-241 7.44E-06 1.52E-12 1.83E-12 1.37E-12 1.19E-12 4.63E-12 1.4/E-12 1.29E-12 1.53E-12 2.4/E-12 2.04E-03 1.58E-07 2.35E-02 1.0SE-02 1.32E-01 6.77E-OB 4.45E-03 9.91E-03 9.91E-03 1.32E-01 Am-241 4.25E-06 1.04E-08 1.29E-08 B.13E-09 6.29E-09 3.46E-OB 9.45E-09 7.65E-09 9.BIE-09 1.54E-08 1.3/E-01 1.13E-05 7.77E-02 7.35E-01 9.17E->-OO 6.76E-06 3.30E-01 5.0IE-01 5.07E-01 9.17E->-OO Totals 1.18E-04 1.35E-04 1.17E-04 1.14E-04 1.94E-04 1.21E-04 1.12E-04 1.21E-04 2.24E-04 1.9/E-01 1.25E-02 1.72E->O0 1.05E->O0 1.24E->01 1.27E-02 4.60E-01 8.BSE-01 8.86E-01 1.24E+01

4440-7380-90-017, Revision 3 Page 14 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Table 12. TMI-2 ABO Fire Case I OJI.site Dose Conseauences External Air Submersion Dose Internal Inhalation Dose Totals Release Maximum Organ Nuclide Gonad Breast Lung Marrow Bone Thyroid Rtnnder Effecti\'e Skin Gonad Breast Lung Marrow Bone Thyroid Rmnder EffectiYe Effective TEDE Bone Total Dose rCi/sl fmreml rmreml rmreml fmreml rmreml lmreml fmreml lmreml lmreml lmrcml rmreml fmreml lmreml /mrcml fmreml fmreml fmreml lmreml lmreml Sr-90 7.99E-05 1.77E-09 2.15E.Q9 1.46E-09 1.23E-09 5.1/E-09 1.66E-09 1.39E-09 1.71E-09 2.09E-06 2.10E-04 2.10E-04 2.27E-01 2.67E-02 5.77E-02 2.10E-04 4.55E-04 2.79E-02 2.79E-02 5.7/E-02 Y-90 7.99E-05 4.29E-08 4.99E-08 4.02E-08 3.68E-08 1.01E-07 4.24E-08 3.81E-08 4.31E-08 1.42E-05 7.56E-07 7.56E-07 7.40E-04 2.22E-05 2.21E-05 7.56E-07 3.07E-04 1.81E-04 1.81E-04 2.22E-05 Cs-137 9.90E-04 2.24E-08 2.72E-08 1.BBE-08 1.S0E-08 6.44E-08 2.12E-08 1.78E-08 2.18E-08 2.43E-05 8.63E-03 7.72E-03 8.69E-03 8.1/E-03 7.82E-03 7.81E-03 8.98E-03 8.50E-03 8.50E-03 7.82E-03 Ba-137m 9.3/E-04 7.51E-05 B.5/E-05 7.45E-05 7.27E-05 1.23E-04 7.67E-05 7.13E-05 7.67E-05 9.93E-05 0.00E..00 0.00E..00 0.00E..00 0.00E..00 0.OOE..00 0.00E..00 0.OOE..00 0.00E..00 7.67E-05 1.23E-04 Tb-230 4.21E-15 2.15E-19 2.B5E-19 1.71E-19 1.46E-19 6.33E-19 1.95E-19 1.64E-19 2.0BE-19 5.39E-19 1.71E-12 1.71E-12 1.26E-09 7.24E-10 9.04E-09 1.71E-12 4.40E-12 3.BBE-10 3.BBE-10 9.04E-09 Th-231 4.35E-14 6.66E-17 8.39E-17 5.38E-17 4.5/E-17 2.01E-16 6.18E-17 5.13E-17 6.45E-17 3.12E-16 3.30E-16 1.30E-16 3.79E-14 3.41E-15 3.99E-14 8.52E-17 1.69E-14 1.03E-14 1.03E-14 4.01E-14 Pa-233 2.31E-11 6.01E-13 6.89E-13 5.83E-13 5.43E-13 1.36E-12 6.04E-13 5.52E-13 6.13E-13 1.09E-12 2.96E-12 2.11E-12 3.90E-10 1.89E-11 1.69E-10 1.29E-12 3.40E-11 5.92E-11 5.99E-11 1.71E-10 U-233 1.0IE-17 5.15E-22 6.77E-22 4.11E-22 3.78E-22 1.26E-21 4.72E-22 3.99E-22 4.9/E-22 1.39E-21 2.71E-16 2.71E-16 3.24E-12 7.S0E-15 1.19E-13 2.71E-16 1.00E-14 3.90E-13 3.90E-13 1.19E-13 U-234 1.B0E-11 4.49E-16 7.36E-16 2.24E-16 2.15E-16 1.02E-15 3.42E-16 2.45E-16 3.90E-16 2.17E-15 4.4/E-10 4.4/E-10 5.33E-06 1.25E-08 1.95E-07 4.47E-10 1.66E-08 6.40E-07 6.40E-07 1.95E-07 U-235 4.35E-14 8.71E-16 1.00E-15 8.34E-16 7.S0E-16 2.27E-15 8.71E-16 7.8/E-16 8.90E-16 1.07E-15 1.03E-12 1.03E-12 1.1BE-08 2.85E-11 4.3/E-10 1.03E-12 3.72E-11 1.44E-09 1.44E-09 4.37E-10 U-236 6.30E-13 1.09E-17 1.97E-17 3.90E-18 4.1/E-18 2.13E-17 7.50E-18 4.83E-18 8.97E-18 6.39E-17 1.49E-11 1.49E-11 1.7/E-07 4.14E-10 6.52E-09 1.49E-11 5.50E-10 2.12E-08 2.12E-08 6.52E-09 U-237 1.33E-10 2.23E-12 2.61E-12 2.0BE-12 1.83E-12 6.40E-12 2.20E-12 1.95E-12 2.26E-12 3.78E-12 1.0BE-11 4.49E-12 6.23E-10 5.46E-11 5.33E-10 3.4/E-12 1.58E-10 1.26E-10 1.29E-10 5.39E-10 Np-237 2.31E-11 6.82E-14 8.27E-14 5.92E-14 5.05E-14 2.10E-13 6.52E-14 5.58E-14 6.76E-14 1.01E-13 6.B0E-07 3.88E-10 3.70E-07 6.02E-06 7.51E-05 3.0BE-10 5.37E-07 3.35E-06 3.35E-06 7.51E-05 Pu-238 2.20E-07 4.10E-12 7.93E-12 6.62E-13 1.05E-12 5.81E-12 2.50E-12 1.24E-12 3.05E-12 2.55E-11 2.27E-03 9.62E-08 7.00E-02 1.27E-02 1.58E-01 B.44E-08 5.99E-03 1.70E-02 1.70E-02 1.58E-01 Pu-239 1.70E-06 2.34E-11 3.64E-11 1.28E-11 1.29E-11 4.57E-11 1.87E-11 1.38E-11 2.05E-11 8.98E-11 2.03E-02 6.74E-07 5.46E-01 1.11E-01 1.39E..O0 6.33E-07 5.10E-02 1.41E-01 1.41E-01 1.39E..O0 Pu-240 8.18E-07 1.48E-11 2.86E-11 2.53E-12 3.83E-12 2.15E-11 9.11E-12 4.55E-12 1.10E-11 9.11E-11 9.76E-03 3.52E-07 2.63E-01 5.34E-02 6.68E-01 3.06E-07 2.46E-02 6.77E-02 6.7/E-02 6.68E-01 Pu-241 5.44E-06 1.11E-12 1.34E-12 1.00E-12 8.69E-13 3.38E-12 1.0BE-12 9.40E-13 1.12E-12 1.B1E-12 1.49E-03 1.16E-07 1.72E-02 7.73E-03 9.62E-02 4.94E-08 3.25E-03 7.24E-03 7.24E-03 9.62E-02 Am-241 3.13E-06 7.62E-09 9.50E-09 5.99E-09 4.63E-09 2.55E-08 6.95E-09 5.63E-09 7.26E-09 1.14E-08 1.01E-01 8.30E-06 5.72E-02 5.41E-01 6.75E..O0 4.9/E-06 2.43E-01 3.73E-01 3.73E-01 6.75E..OO Totals 7.51E-05 8.58E-05 7.46E-05 7.27E-05 1.23E-04 7.6/E-05 7.14E-05 7.6/E-05 1.40E-04 1.44E-01 7.94E-03 1.19E..OO 7.61E-01 9.12E..O0 8.03E-03 3.38E-01 6.42E-01 6.42E-01 9.12E+00

4440-7380-90-0I 7, Re\':ision 3 Page 15 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms Table 13. TMI-2 FfC Fire Case 1 Offsite Dose Conseauences E."<temal Air Submersion Dose Internal Inhalation Dose Totals Release Maximum Organ Nuclide Gouad Breast Lung Marrow Bone TI1yroid Rmnder Effective Skin Gonad Breast Lung Marrow Bone Thyroid Rmnder Effective EITectivc TEDE Bone Total Dose rci/sl rmreml rmreml rmreml rmreml rmreml rmreml rmrcml rmreml rmreml rmrcml rmrcml rmrcml rmreml rmreml rmrcml rmreml rmreml rmreml rmreml Sr-90 1.97E-05 4.35E-10 5.31E-10 3.S0E-10 3.04E-10 1.28E-09 4.10E-10 3.42E-10 4.21E-10 5.15E-07 5.17E-05 5.17E-05 5.S0E-02 6.58E-03 1.42E-02 5.17E-05 1.12E-04 6.BBE-03 6.BBE-03 1.42E-02 Y-90 1.97E-05 1.0SE-08 1.23E-08 9.91E-09 9.07E-09 2.49E-08 1.05E-0B 9.41E-09 1.0SE-08 3.49E-06 1.87E-07 1.87E-07 1.82E-04 5.47E-06 5.45E-06 1.87E-07 7.58E-05 4.47E-05 4.47E-05 5.47E-06 Cs-137 2.48E-05 5.60E-10 6.B0E-10 4.70E-10 4.01E-10 1.61E-09 5.31E-10 4.46E-10 5.44E-10 6.07E-07 2.16E-04 1.93E-04 2.17E-04 2.04E-04 1.95E-04 1.95E-04 2.25E-04 2.12E-04 2.12E-04 1.95E-04 Ba-137m 2.34E-05 1.BBE-06 2.14E-06 1.86E-06 1.B2E-06 3.0BE-06 1.92E-06 1.78E-06 1.92E-06 2.48E-06 0.OOE..00 0.OOE..00 0.00E..00 0.00E..00 0.OOE..00 0.OOE..00 0.00E..00 0.OOE..00 1.92E-06 3.0BE-06 Th-230 2.34E-15 1.20E-19 1.58E-19 9.50E-20 B.11E-20 3.51E-19 1.0BE-19 9.10E-20 1.16E-19 3.00E-19 9.49E-13 9.49E-13 6.98E-10 4.02E-10 5.02E-09 9.49E-13 2.44E-12 2.05E-10 2.05E-10 5 02E-09 Th-231 2.25E-14 3.45E-17 4.34E-17 2.78E-17 2.37E-17 1.04E-16 3.20E-17 2.66E-17 3.34E-17 1.61E-16 1.71E-16 6.72E-17 1.96E-14 1.76E-15 2.0SE-14 4.41E-17 B.76E-15 5.31E-15 5.34E-15 2.0BE-14 Pa-233 1.24E-11 3.22E-13 3.69E-13 3.12E-13 2.91E-13 7.31E-13 3.24E-13 2.96E-13 3.29E-13 5.83E-13 1.59E-12 1.13E-12 2.09E-10 1.01E-11 9.07E-11 6.91E-13 1.82E-11 3.17E-11 3.21E-11 9.14E-11 U-233 5.75E-18 2.76E-22 3.63E-22 2.20E-22 2.02E-22 6.73E-22 2.53E-22 2.14E-22 2.66E-22 7.46E-22 1.45E-16 1.45E-16 1.74E-12 4.07E-15 6.40E-14 1.45E-16 5.37E-15 2.09E-13 2.09E-13 6.40E-14 U-234 9.99E-12 2.50E-16 4.09E-16 1.24E-16 1.19E-16 5.65E-16 1.90E-16 1.36E-16 2.17E-16 1.21E-15 2.48E-10 2.4BE-10 2.96E-06 6.94E-09 1.0BE-07 2.4BE-10 9.20E-09 3.56E-07 3.56E-07 1.0BE-07 U-235 2.25E-14 4.51E-16 5.19E-16 4.32E-16 3.94E-16 1.18E-15 4.51E-16 4.0BE-16 4.61E-16 5.53E-16 5.31E-13 5.33E-13 6.11E-09 1.47E-11 2.26E-10 5.31E-13 1.92E-11 7.44E-10 7.44E-10 2.26E-10 U-236 3.31E-13 5.73E-18 1.03E-17 2 05E-18 2.19E-18 1.12E-17 3.93E-18 2 53E-18 4.70E-18 3.35E-17 7.79E-12 7.79E-12 9.27E-08 2.17E-10 3 42E-09 7.79E-12 2.BBE-10 1.11E-08 1.11E-0B 3.42E-09 U-237 7.02E-11 1.18E-12 1.3BE-12 1.09E-12 9.61E-13 3.37E-12 1.16E-12 1.03E-12 1.19E-12 1.99E-12 5.69E-12 2.37E-12 3.2BE-10 2.B7E-11 2.B0E-10 1.83E-12 8.30E-11 6.66E-11 6.78E-11 2.B4E-10 Np-237 1.24E-11 3.66E-14 4.43E-14 3.17E-14 2.l0E-14 1.12E-13 3.49E-14 2.99E-14 3.62E-14 5.41E-14 3.64E-07 2.0BE-10 1.98E-07 3.22E-06 4.02E-05 1.65E-10 2.BBE-07 1.B0E-06 1.B0E-06 4.02E-05 Pu-238 1.22E-07 2.28E-12 4.41E-12 3.68E-13 5.83E-13 3.23E-12 1.39E-12 6.91E-13 1.69E-12 1.42E-11 1.26E-03 5.34E-08 3.89E-02 7.04E-03 8.81E-02 4.69E-OB 3.33E-03 9.46E-03 9.48E-03 B.81E-02 Pu-239 8.79E-07 1.21E-11 1.B9E-11 6.62E-12 6.67E-12 2.37E-11 9.69E-12 7.14E-12 1.0SE-11 4.65E-11 1.05E-02 3.49E-07 2.82E-01 5.74E-02 7.18E-01 3.2BE-07 2.64E-02 7.28E-02 7.2BE-02 7.18E-01 Pu-240 4.29E-07 7.75E-12 1.50E-11 1.33E-12 2.01E-12 1.13E-11 4.7BE-12 2.39E-12 5.79E-12 4.78E-11 5.12E-03 1.85E-07 1.3BE-01 2.B0E-02 3.50E-01 1.60E-07 1.29E-02 3.55E-02 3.55E-02 3.50E-01 Pu-241 2.86E-06 5.84E-13 7.05E-13 5.27E-13 ~.58E-13 1.78E-12 5.67E-13 4.95E-13 5.89E-13 9.51E-13 7.85E-04 6.09E-OB 9.04E-03 4.07E-03 5.06E-02 2.60E-OB 1.71E-03 3.81E-03 3.B1E-03 5.0SE-02 Am-241 1.67E-06 4.07E-09 5.0BE-09 3.20E-09 2.47E-09 1.36E-OB 3.72E-09 3.01E-09 3.BBE-09 6.07E-09 5.40E-02 4.44E-06 3.0SE-02 2.89E-01 3.S0E..00 2.66E-06 1.30E-01 1.99E-01 1.99E-01 3.S0E..00 Totals 1.89E-06 2.16E-06 1.BBE-06 1.83E-06 3.12E-06 1.93E-06 1.B0E-06 1.93E-06 7.10E-06 7.19E-02 2.50E-04 5.55E-01 3.92E-01 4.83E..OO 2.50E-04 1.75E-01 3.28E-01 3.28E-01 4.83E+00

4440-7380-90-017, Revision 3 Page 16 ofl7 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 8.0 RESULTS 8.1 Case 1 Results Case 1 purge doses are calculated for the four reactor building areas in Tables 10 through 13 . In all cases the bone surface is the critical organ. External air submersion dose is insignificant relative to internal inhalation dose. The critical nuclide in this analysis is Am-241. The fact that Am-241 acthrity has increased in the past 26 years combines with relatively high dose conversion factors to make it the primary dose contributor. Although most of the other radionuclides have been diminished due to 26 years ofradiodecay, the maximum organ dose calculated (12.4 mrem) in this revision is not muc h lower than that reported in Revision 2 of this calculation (13.5 mrem). This is due to several factors. The first factor is the increased Am-241 activity as discussed previously. The second factor is the dose co nversion factors used in this revision of the calculation (FGR-11 and FGR-12) are generally higher than tho se used in Revision 2 of the calculation.

Reference 4.4 includes an attached table that presents the calculation of the Case 1 BAS fi re dose. In this table a dose conversion factor of 4.80E+ 12 mremlCi is used for the Am-241 inhalation do se. In this revision of the calculation, the inhalation dose conversion factor from FGR-11 [Ref. 4.7] fior Am-241 is equivalent to 8.04E+ 12 mremlCi. This increase is representative of the other nuclides analyzed and is a significant factor as to why the dose had decreased relatively little. The following table pre sents the TEDE and bone dose for the four fire scenarios of Case 1. The bounding values are in bold Table 14. TMI-2 Case 1 Fire Dose Results OP Fire BAS Fire ABD Fire FTC Fi re Dose Type mrem [mrem mrem mrem11 TEDE 0.970 0.886 0.642 0.328 Bone Dose 12.1 12.4 9.12 4.83 The doses presented in Table 14 credit 99% efficient HEPA filtration of per Assumption 3 .4. To estimate offsite dose without crediting HEPA filtration, the Table 14 doses are multiplied by 100 to negate the effect of HEPA filtration.

Table 15. TMI-2 Case 1 Fire Dose Results with No HEPA Filters OP Fire BAS Fire ABD Fire FTC Fi re Dose Type mrem] [mrem] [mrem] [mrem ]

TEDE 97.0 88.6 64.2 32.8 Bone Dose 1,210 1,240 912 483 8.2 Case 2 Results As discussed in Section 6.3, new Case 2 numerical analysis was not performed as part ofthis revision to the calculation. Table 16 presents the Revision 2, Case 2 dose results [Ref. 4.2], which rem ain valid. The slow, 14 hour1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months release considers multiple exposure pathways as dictated by Appendix I of 10 CFR 50 [Ref.

4.20].

Table 16. TMI-2 Case 2, Revision 2 Fire Dose Results OP Fire BAS Fire ABD Fire FTC Fi re Dose Type mrem mrem mrem mrem.l Total Bod 0.777 0.272 0.167 NIA Bone Dose 3.01 1.02 0.628 NIA Note that Revision 2 of the calculation did not calculate TEDE, but does report total body dose, which can be compared to total body dose limits. Also note that Revision 2 did not perform Case 2 an alysis for the FTC fire scenario because there is no ignition source in that area during PDMS [Ref. 4.4].

4440-7380-90-017, Revision 3 Page 17 of 17 PDMS SAR Section 8.2.5 Fire Analysis Source Terms 8.3 Case 3 Results As discussed in Section 6.4, Case 3 numerical analysis was not performed because it is bounded by Case 1 analysis. Thus dose results for Case 3 are no higher than those of Case 1.

9.0 CONCLUSION

S The bounding case for the TMI-2 reactor building fire is Case 1, the fire during reactor building purge event. Case 1 bounds Cases 2 and 3. This is due to the forced, instantaneous release of radioactivity to the environment through the HEPA filters. Considering fires in four reactor building areas, the maximum TEDE is 0.970 mrem and the maximum organ dose is 12.4 mrem to bone (see Table 14). These doses are below the dose criteria limits provided in Section 1.1 including the TMI-2 administrative dose limits of 5 mrem TEDE (body) and 15 mrem organ dose.

The Case 2 and Case 3 dose results from Revision 2 of this calculation [Ref. 4.2] remain valid and are also below the dose criteria limits provided in Section 1.1.

For the consideration of no HEPA filters, the maximum doses are one hundred times the HEPA-credited Case 1 doses or 97 mrem TEDE and 1,240 mrem to bone. These doses exceed the TMI-2 administrative dose limits. Given the instantaneous nature of the Case 1 doses, they can be considered to occur in less than an hour. Thus the 97 mrem TEDE exceeds the 10 CFR 20 hourly limit of2 mrem TEDE.

10.0 ATTACHMENTS Attachment A: Revision 2 of 4440-7380-90-017 ........................................................ Page Al-A83 Attachment B: TODI 5971-2019:002, Fire Dose Calculation Design Inputs ................. Page Bl-B2 Attachment C: Memo C312-93-1015, TMI-2 RB Surface Contamination Activity ....... Page Cl-C4

4440-7380-90-017 Revision 3 Attachment A Page A 1 of A83 Gil!]Nuctearl TMI Environmental Controls Number Polic and Procedure Manual 6615-ADM-4500.ll Title Revision No.

Calculations Review Procedure 0 EXHIBIT l THREE MILE ISLAND ENVIRONMENTAL CONTROLS CALCULATION REVIEW/COVER SHEET SUBJECT PA WIS SA/c... 4mn, ~ 11in1e.>1t 14 ~ C/4-v: F~ (£B), 0 r P~Ci~BJ-r- ~ R B ~ - Cai.c. pf; 9.~~015

/t /

~1 9-/ ?-9-1.,

I Data Approved ay t,1tltl/#1CefPSs/£i;eI Print/Signature

~ ~I Form 6615-ADM-.4500.11-1 306Sd 4440-7380-90-oftRetision 2

4440-7380-90-017 Revision 3 Attachment A Page A2 of A83

[a]2]Nuclear Memorandum

Subject:

Dose Calculation Results per Date: October 27, 1992 memo C312-92-1045, PDMS SAR Rev. 16 From: Stephen Acker Location: TMI - EOF Environmental Scientist, TMI 6615-92-160 To: Ed Schrull Licensing Engineer, TMI-2 The dose calculations for revision 16 to the Unit 2 PDMS SAR have been completed per your request. I have edited the associated pages and tables from Chapter 8 of the SAR to reflect the updated source terms.

The methods and results can be referenced in Cale# 92-015. Please contact me if you have any questions regarding these calculations.

Stephen Acker Extension 540-4526 cc Beverly A. Good File: 3.9.2 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A3 of A83 CHAPTER 8 TABLE OF CONTENTS (Cont'd)

LIST OF TABLES TABLE NO. TITLE PAGE 8.1-1

SUMMARY

OF SOURCE TERMS a. 1-9 8.1-2 ESTIMATES OF Cs AND Sr INVENTORY OF 8.1-10 SELECTED REACTOR BUILDING LOCATIONS 8.1-3 Ci FRACTIONS IN RESIDUAL FUEL 8.1-11

8. 1-4 MAXIMUM POTENTIAL DOSES ESTIMATED FROM ev.1+1" "- 8.1-12 EFFLUENT RELEASES 8.1-5 ESTIMATED DOSE COMMITMENTS RESULTING FROM 8. l-12a ROUTINE AND UNANTICIPATED EVENTS DURING PDMS ii AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A4 of A83 For the initial conditions of interest (i.e., negligibly small concentrations at the beginning and no purge flow during this period), this equation has the simple solution:

Where si = Slv The source and depletion parameters in this equation which approximate the observed behavior following the krypton purge are:

fs = 5.0 E-11 (µCi/cc/day) for Cs-137 Es= 1.5 E-11 (qCi/cc/day) for Sr-90, and Ey = .005 (day- ) for both isotopes If the Reactor Building atmosphere was allowed to reach equilibrium (i.e.,

previously prevented by personnel entries, associated "mini-purges," and other activities) the equilibrium concentration would be:

The above source and sink estimates would predict equilibria at 1.0E-8 and 3.0E-9

µCi/cc, respectively, for Cs-137 and Sr-90.

These values are considered conservative as they exceed the actually observed levels at any time after initial accident conditions. The removal of many of the potential sources of Cs and Sr in the Reactor Building resulting from the decontamination of large surfaces areas, removal of the basement water and sediment, and flushing and sealing of contaminated systems prior to PDMS, has resulted in further reductions in airborne concentrations during PDMS.

8.1.3 OFF-SITE DOSE ESTIM.TE~ jZ.o.,.fi" 04.

~*a*

r~!,"tl-\ ~ ...+e.JL .--*

Environmental doses fromlreleases were,quantified with the SEEDS code. This is the model. used to estimate "'doses for quarterly reports to the NRC., and for

.-emergency -~~--ca.ku-lc1Lio11~ ro, TMl-2. . The accuracy o~ the SEED~ c_ode ".'a~ _ I documented m Reference 8.1 1. -r f* . . -~-. ~ **,

Le-/. z::c;-..t,e ;* c, "-~.=-- --:..,!.! -~i--!l-*-.:.-:.;~1~1...w..,-.,.,.--:*,--::,...._..,:.t). .. *~ -

This model calculates the dispersion of radionuclides in three ways: nol"llal * --

airborne dispersion (X/Q), depleted dispersion (i.e., which accounts for various removal processes like settling out), and deposition (D/Q).

The SEEDS calculations use the "delta T", or the difference in temperature between sensors at 33 feet and 150 feet, of the on-site meteorological tower to determine the atmospheric (Pasquill) stability class. The ,npdel then uses the stability class with other meteorological parameters such as wind speed and direction along with plant parameters including stack height, stack diameter, and stack flow rate to determine the atmospheric dispersion.

8.1-5 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A5 of A83 The meteorological data used by SEEDS are automatically collected from the on-site tower and stored electronically for future use. Each meteorological tower sensor (there are about 20) is polled by a computer every 10 seconds. The ten-second results are averaged iflto a 15 minute average. The fifteen minute averages centered on the hour are used as hourly values. The hourly values are used for routine dose calculations.

To calculate the dose to the public, SEEDS employs numerous data files which describe the area around THI in tenns of population distribution and foodstuffs production. The area around TMI is subdivided into sixteen ~qual meteorological sectors (N, NNE, NE, ENE, E, ESE, etc.). Each sector is then represented in each set of data files and dispersion is calculated for each sector separately. Data files include such infonnation as the distance from the plant vent to the site boundary in each sector, the population groupings, and the location of milk cows, milk goats, gardens of more than 500 square feet and meat animals.

SEEDS also contains dose conversion factors for 75 radionuclides for each of four age groups (adults, teenagers, children and infants), seven pathways (inhalation, ground deposition, plume direct dose, and ingestion of cow milk, goat milk, vegetables, and meats), and eight organs (total body, thyroid, liver, skin, kidney, lung, bone, and GI). The pathways, organs and age groups are those specified in Regulatory Guide 1.109.

The atmospheric dispersion is combined with the dose conversion factors and applied to each organ, age group, and pathway to estimate the dose to an individual by integrating by sector, distance, and time (meteorology changes) to detennine the dose, distance and direction to the maximally-exposed individual.

8.1.3.1 Routine Releases The off-site doses resulting from routine releases of gaseous fission products and transuranics were estimated by combining the annual release source tenn discussed in Section 8.1.2.3 and summarized in Table 8.1-1, averaged over the year, with the hourly 1985 meteorological data from the TMI tower. The calculation, therefore, is based on about"8600 different sets of meteorological conditions.

Liquid pathway doses were evaluated using MIDAS (a precursor to SEEDS), based on the 94 year average Susquehanna River flow. MIDAS liquid dose calculations consider three pathways: fish ingestion, water ingestion, and shoreline exposure.

The eight organs and. four age groups of Regulatory Guide 1.109 also were used.

For comparison, the largest potential doses which could be postulated on the basis of the actual effluent measurements for TMI Units 1 and 2 are shown in Table 8.1-4 for several recent years. It should be noted that the calculated values on this table are hypothetical doses which could be accrued to a maximally-exposed individual on the basis of the measured effluents from TMI-2. The comparison of these calculated doses with the estimated PDMS doses on Table 8.1-4 shows that actual airborne releases from TMI-2 during recent cleanup activities were generally smaller than the projections made for PDMS. It is concluded, therefore, that the estimated values of Table 8.1-5 are conservative estimates of the likely 8.1-6 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A6 of A83 impact of PDMS on the environment. Nevertheless, the estimated doses for PDMS are such small fractions of the normal background doses that they can be considered insignificant.

8.1.3.2 Unanticipated Releases The off-site doses from unanticipated events have been calculated using SEEDS and other Regulatory Guide 1.109 based calculation methods (e.g., MIDAS). Off-site doses from releases which are described as instantaneous puffs in Section 8.2 were calculated -f<'.:>C 1e-emeY:-geAcy.-dose-as.ses.sment_r:ou.tine._in SEEDS and other.._codes--

aRd are eases en aR acute inhalation exposure only. The calculation is based on the actua 1 expected station ventilation fl owrate and assumes a very stable G c 1ass stability to maximize the off-site concentration estimates. The actual calculated X/Q for these conditions of 7.67E-4 sec/cubic meter was used. Due to the short duration, the other pathways included in the Regulatory Guide 1.109 Appendix I calculation are not considered for instantaneous releases.

The off-site doses from other than puff releases (i.e., 80 minute or longer unanticipated airborne releases) have been evaluated using SEEDS. A 14-hour period of very stable conditions was selected at random from the 1985 TMI-2 meteorological data. The selection of this data maximized off-site concentration estimates and allows the inclusion of the ingestion pathways into the total dose estimate. The release source terms given in Section 8.2 were averaged over the 14-hour period. . * . ,, l

,,ic:.1-eoni

. 1v;fl

. L-Finally, the long-term (i.e., 3 month) release for the open penetrat'!.QD*event was also evaluated using SEEDS. In this case, six RleRtRs ef 1986*--aatafrom the TMI tower (J..d-, 1 to September 30) was used. The selection of this data provides a best estimate of the expected dose from a calendar quarter while maximizing some effects such as animal grazing periods. The release source terms given in Section 8.2 were averaged over the K month period.

3 8.1-7 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

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Critical Organ Dose 2E-3 l.4E-2 4. lE-3 3.2E-3 5.0E-3 10

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Critical Organ Dose l.IE-2 1.BE-3 2.2E-3 1. 7E-2 2.4E-2 15 tritical Organ Liver Total Total Bone Bone Body Body

NOTE: The PDMS dose limits were derived from applicable dose limits established in 10 CFR 50 Appendix I. -0 (C

CD 2:i 8,

8.1-12 AM. 9 - OCTOBER 1990 ~

w

4440-7380-90-017 Revision 3 Attachment A Page A8 of A83 TABLE 8.1-5 ESTIMATED DOSE COMMITMENTS RESULTING FROM. ROUTINE AND UNANTICIPATED EVENTS DURING PDHS I. POPULATION DOSES Person-rem/year Population doses from routfae, releases via airborne pathway:

Bone Dose 0.14 o. ,11 Total Body Dose 0.04 t).o"I Population doses from routine releases via liquid pathway:

Bone Dose 0.09 Total Body Dose 0.02 Total population dose:

Bone Dose 0.23 Total Body Dose 0,06 II. DOSES TO MAXIMALLY-EXPOSED INDIVIDUA~ mrem/year Dose from routine releases via airborne pathway:

Bone Dose Total Body Dose Dose from'ratreine releases via liquid pathway.

Bone Dose o.oos Total Body Dose 0.002 III. MAXIMUM UNANTICIPATED RELEASE Dose to maximally-exposed individual from unanticipated event release _Ja,,: mrem (bone dose limiting - inhalation only) 13 .. .5

8. l-12a AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A9 of A83 ISOTOPE CURIES Sr-90 4.SE-4 Cs-137 2. lE-3 Pu-238 4.7E-7 Pu-239 5.SE-6 Pu-240 1.SE-6 Pu-241 6.7E-5 Am-241 l.lE-6 This postulated release results in a calculated dose to the maximally-exposed individual of 13.8 mrem (Reference 8.2-1). This dose includes the inha"lation pathway only.

Case 2 - Reactor Building at negative pressure For this case, it is assumed that the Reactor Building is isolated and is being held at a slightly negative pressure. It is assumed that the postulated fire distributes a portion of the contamination to the Reactor Building atmosphere.

However, in this case, the Reactor Building is isolated and the source term release fraction is contained within the Reactor Building and diffused within the Reactor Building atmosphere. It is then assumed that the Reactor Building Purge is actuated and the source term release fraction is exhausted over a period of time through the Reactor Building Purge HEPA filters assuming a 99% filter efficiency. It is also assumed that no settling of the distributed contamination occurs and the total source term release fraction is exhausted to the environment in the first Reactor Building air change subsequent to the actuation of the Reactor Building Purge. In addition to the source term from the postulated fire, the source term attributable to one normal Reactor Building volume must also be included in the total release. All fire zones in the Containment were analyzed with respect to resultant off-site dose. For this case, the analysis of a postulated fire involving the combined 305' and 347' elevations of the Reactor Building produced the highest dose to the maximally exposed individual. The postulated release to the environment is as follows:

ISOTOPE CURIES Sr-90 1.lE-3 Cs-137 3.2E-3 Pu-238 2.9E-7 Pu-239 3.4E-6 Pu-240 9, lE-7 Pu-241 4. lE-5 Am-241 6.SE-7 This postulated release results in a calculated dose to the maximally-exposed individual of ,.xf-mrem (Reference 8.2-1). This dose includes all applicable Appendix I pathways,\,

. --!J, 0 8.2-10 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A10 of A83 This results in a release to the environment of:

ISOTOPE CURIES Sr-90 4.2E-4 Cs-137 1.4E-3 Pu-238 2.4E-9 Pu-239 2.7E-B Pu-240 7.3E-9 Pu-241 3.4E-7 Am-241 5.5E-9 This postulated release results in a calculated dose to the maximally-exposed individual of-3-.-aE-l mrem. This dose includes all applicable Appendix I pathways.

'l,S'f - I 8.2-12 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A11 of A83

(?iijl)Nuclear Memorandum

Subject:

Dose Calculations Date: July 13, 1992 From: E. D. Schrull - Licensing Engineer Location: SOB C312-92-1045 To: B. A. Good - Manager, Environmental Controls C~ i**'/!';!,,,vt4,.,L TMI-2 Licensing has recently revised source term calculations for u various scenarios. Detailed on Attachment 1 are: 1) source terms for/

,~~ "1~--<-.~ a postulated ffre in each of four fire zones in the Reactor Building

_ (RB); 2) the source term for a release from the RB due to an open C°.,(AL ~113l/-:;,,<!f)N2t penetration; and 3) the annual routine release transuranic source term.

/, " For the routine release source term, the transuranic values should be

/~ combined with the Cs and Sr values given in PDMS SA.R Table 8.1-1. The subsequent dose calculation should yield results that can be incorporated into PDMS SAR Tables 8.1-4 and 8.1-5. Also, please perform PDMS SAR-type dose calculations (i.e., inhalation only and all applicable Appendix I pathways) for each of the other events.

Please contact me if you have any questions.

E. D. Schru 11 Extension 8428 dlb Attachment cc: S. E. Acker - Environmental Scientist III R. E. Rogan - TMI Licensing Director J~ S. Schork - Licensing Engineer CARIRS - TMI 4440-7380-90-017 Revision 2

ATTACHMENT 1

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4440-7380-90-017 Revision 3 Attachment A Page A15 of A83 TABLE 8.1-3 Ci FRACTIONS IN RESIDUAL FUEL ISOTOPE Ci FRACTION Pu-238 6.30 E-3 Pu-239 7.32 E-2 Pu-240 1.94 E-2 Pu-241 8.87 E-1 Am-241 1.40 E-2 TOTAL 1.00 8.1-11 AM. 9 - OCTOBER 1990 4440-7380-90-017 Revision 2

Attachment A Page A16 of A83 4440-7380-90-017 Revision 3

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4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A17 of A83

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4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A18 of A83 THREE MILE ISLAND UNIT 2ATMOSPHERIC BATCHES PRINTED 09-18-1992 BATCH ID: 92PDMSDR.......- .A.J-G b-~ ?~ ~

START DATE: 8506181700v STOP DATE: 8506190700~

RELEASE POINT: 1v ISOTOPE ACTIVITY uci/sec ACTIVITY uCi

/-~ 7 /.~

SR90v 2.976E-03 1. SOOE+02 CS137v 3.571E-02 l.800E+03 PU238v S.357E-06 2. 700E- Olv PU239v 3.373E-05 1. 700E+00"'"

PU240v 1.627E-05 8.200E-Olv PU24lv 3.770E-04 1. 900E+Ol AM241 S.556E-05 2.BOOE+OO 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A19 of A83 THREE MILE ISLAND UNIT 2ATMOSPHERIC BATCHES PRINTED 09-18-1992 BATCH ID: 920PFIREv START DATE: 8506181700 STOP DATE: 8506190700v RELEASE POINT: lv ISOTOPE ACTIVITY uCi/sec ACTIVITY uCi SR90' 1.806E-02 9 .100E+02 V

CS137v 5.952E-02 3. OOOE+03V" PU238v 6.944E-06 3.500E-Olv-PU239 4.365E-05 2.200E+OOV-PU240 2.183E-05 1.lOOE+OO PU241/ 4.960E-04 2. 500E+01 AM241 7.143E-05 3. 600E+OO 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A20 of A83 THREE MILE ISLAND UNIT 2ATMOSPHERIC BATCHES PRINTED 09-18-1992 BATCH ID: 92PDMSBAv START DATE: 8506181700v STOP DATE: 8506190700 RELEASE POINT: 1 ...,,

ISOTOPE ACTIVITY uCi/sec ACTIVITY uCi SR90 4.960E-03 2.500E+02v CS137~ 5.556E-02 2.800E+03v PU238/ 7.341E-06 3.700E-01""

PU239.,. 4. 563E- 05 2.300E+00v PU240v 2.183E-05 1.l00E+oov PU241V 5.159E-04 2.600E+01V AM241V 7.540E-05 3.800E+0Q/

4440-7380-90-017 Revision 2

Attachment A Page A21 of A83 THREE UNIT 2ATMOS PRINTED 09-18-1992 BATCH SBA START DA STOP DATE RELEASE PO ISOTOPE AC ACTIVITY uCi SR90 2.500E+02 CS137 2.800E+03 PU238 . 3.700E-01 PU23 4.563E-05 2.300E+OO PU 2.183E-05 lOOE+OO 5.159E-04 2. OE+Ol 7.540E-05 3.80 +00 BATCH ID: 16PDMSOP START DATE: 8607010000

~

STOP DATE : 8609302359V" RELEASE POINT: 2 ISOTOPE ACTIVITY uCi/sec ACTIVITY uCi j SR90v 5.284E-05 4.200E+02..,.

CS137 1.761E-04 1.400E+03v 3~ -

PU238 1.384E-10 l. lOOE- 03-r PU239 1.635E-09 1. 300E- 02..,.

PU240 4.277E-10 3.400E-03.v PU241~ 1.887E-08 1.SOOE-01 AM241 3.019E-10 2.400E-03 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A22 of A83 THREE MILE ISLAND UNIT 2ATMOSPHERIC BATCHES PRINTED 09-17-1992 BATCH ID: PDMS160Pv START DATE: 8604010000 STOP DATE: 8609302300 RELEASE POINT: 2 v ISOTOPE ACTIVITY uCi/sec ACTIVITY uCi SR90 ,/ 2. 657E-05 4.200E+02.,..

CS137v 8.856E-05 1.400E+03 PU238v 6.959E-ll 1. lOOE- 03"'

PU239v 8.224E-10 1.30DE-02,,,

PU240 2.151E-10 3.400E-03 PU241v 9.489E-09 1.SOOE-01 AM241 l.518E-10 2.400E-03 BATCH ID: PDMS16RR START DATE: 8501010000 STOP DATE: 8512312359 RELEASE POINT: 1/

ISOTOPE ACTIVITY uCi/sec ACTIVITY uCi PU238 2.797E-12 8.820E-05 PU239 3.234E-ll l.020E-03 PU240v 8.625E-12 2. 720E- 04 PU241 3.932E-10 1. 240E- 02 AM241 6. 215E-12 1.960E-Q4/

CS137v 8.879E-06 2.800E+02 SR9Qv 2.695E-06 8.SOOE+Ol /

4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A23 of A83 DOSE CALCULATIONS BASED ON ENVIRONMENTAL SAMPLE RESULTS VERSION: 92.0 BASED ON REGULATORY GUIDE 1.109, NUREG 0172, AND NUREG/CR3535 09-17-1992 b- , ,"O F"/re...

INHALATION PATHWAY FOR 1.157407E-05 DAYS [I~)

BASED ON SINGLE ACUTE RELEASE INTEGRATION ISOTOPE ACTIVITY IN PCI/CUMETER SR90....- 1.lSOE+QSv CS137v 1.380E+Q6v PU238v 2.070E+02 PU239.., 1. 300E+03 PU240 6 .290E+02v PU241'1' l.460E+04 AM241 2 .150E+03 ORGAN TOTAL DOSE COMMITMENT (MR.EM) FOR MAXIMUM INDIVIDUAL INFANT CHILD TEEN ADULT BONE. 1.843E+OO 2.998E+OD 6.759E+OO 7.207E+OO LIVER 7.356E-01 1. 394E+OO 2.128E+OO 2.463E+OO TOT BODY 1.554E-01 2.216E-01 3.964E-01 4.353E-01 THYROID 4.577E-03 4.784E-03 4.678E-03 4.474E-03 KIDNEY 1.211E-02 1.714E-02 1. ?98E- 02 1.421E-02 LUNG 2.239E-01 1. 23 BE- 01 1.207E-01 8.081E-02 GI-LLI 5.629E-03 5.675E-03 5.529E-03 5.306E-03 MAXIMUM ORGAN MAXIMUM AGEGROUP MAXIMUM DOSE BONE ADULT 7.207E+OO X /. 3 7::: Cj_'if~ mre..W'\

l 13~/:d ~

l 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A24 of A83 DOSE CALCULATIONS BASED ON ENVIRONMENTAL SAMPLE RESULTS VERSION: 92.0 BASED ON REGULATORY GUIDE 1.109, NUREG 0172, AND NUREG/CR3535 09-17-1992 01 0e..ck ;~ re_

INHALATION PATHWAY FOR 1.157407E- 05 DAYS (1.1Lc.)

BASED ON SINGLE ACUTE RELEASE INTEGRATION ISOTOPE ACTIVITY IN PCI/CUMETER SR90 6. 980E+os CS137v 2. 300E+06 PU238v 2.680E+02 PU239 1.690E+03 PU240v 8 .440E+02 PU241v 1.920E+04 AM24111' 2. 760E+03 ORGAN TOTAL DOSE COMMITMENT (MR.EM) FOR MAXIMUM INDIVIDUAL INFANT CHILD TEEN ADULT BONE 2.697E+00 4.096E+00 9.668E+00 9.876E+00 LIVER 9.653E-01 1.823E+00 2.772E+00 3.202E+00 TOT BODY 2.247E-01 3.060E-01 5.673E-01 6.144E-01 THYROID 7.411E-03 8.0BSE-03 7.418E-03 7.181E-03 KIDNEY 1.997E-02 2.867E-02 2.959E-02 2.340E-02 LUNG 2.949E-01 1.650E-01 1.608E-01 l.0B0E-01 GI-LLI 1.123E-02 l.194E- 02 l.039E-02 1. 0l0E- 02 MAXIMUM ORGAN MAXIMUM AGEGROUP MAXIMUM DOSE BONE ADULT 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A25 of A83 DOSE CALCULATIONS BASED ON ENVIRONMENTAL SAMPLE RESULTS VERSION: 92.0 BASED ON REGULATORY GUIDE 1.109, IDrn.EG 0172, AND NUREG/CR3535 09-17-1992 I ~-r~

f \.,_

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INHALATION PATHWAY FOR l.157407E-05 DAYS(i~}

BASED ON SINGLE ACUTE RELEASE INTEGRATION ISOTOPE ACTIVITY IN PCI/CUMETER SR90.r 2. 840E+04 CS137 3.450E+04 PU238 l.150E+02 PU239 6. 750E+02 PU240"' 3.300E+02 PU241 .7. 670E+03 AM241.,... l .150E+03 /

ORGAN TOTAL DOSE COMMITMENT (MR.EM) FOR MAXIMUM INDIVIDUAL INFANT CHILD TEEN ADULT BONE 9.455E-01 l.553E+OO 3.506E+OO 3.767E+.OO LIVER 3.763E-Ol 7.209E-01 l.llOE+OO 1.293E+OO TOT BODY 7.996E-02 1.135E-01 2.000E-01 2.183E-01 THYROID 2.335E-03 2.419E-03 2.395E-03 2.285E-03 KIDNEY 2.523E-03 2.728E-03 2.727E-03 2.528E-03 LUNG 1.169E-01 6.311E-02 6.119E-02 4.104E-02 GI-LLI 2.718E-03 2.655E-03 2.556E-03 2.440E-03 MAXIMUM ORGAN MAXIMUM AGEGROUP MAXIMUM DOSE BONE ADULT 3. 767E+OO X. / 3>) - 5*.

1 J' w, rev.,

4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A26 of A83 DOSE CALCULATIONS BASED ON ENVIRONMENTAL SAMPLE RESULTS VERSION: 92.0 BASED ON REGULATORY GUIDE 1.109, NUREG 0172, AND NUREG/CR3535 09-17-1992 BCV~ F A/IJ2__

INHALATION PATHWAY FOR 1.157407E-05 DAYS BASED ON SINGLE ACUTE RELEASE INTEGRATION ISOTOPE ACTIVITY IN PCI/CUMETER SR90 1.920E+os...-

CS137V .2.1soE+06V" PU238 2. 840E+02.,

PU239" 1.760E+03V PU240" 8.440E+02v PU241" 1.990E+04 AM241"" 2.910E+03 ORGAN TOTAL DOSE COMMITMENT (MR.EM} FOR MAXIMUM INDIVIDUAL INFANT CHILD TEEN ADULT BONE 2.518E+OO 4.076E+OO 9.209E+OO 9.789E+OO LIVER 1.00lE+OO 1.894E+OO 2.888E+OO 3.339E+OO TOT BODY 2.121E-01 3.020E-01 S.423E-01 S.957E-01 THYROID 6.290E-03 6.596E-03 6.419E-03 6.144E-03 KIDNEY 1. 803E-02 2.584E-02 2.714E-02 2.131E-02 LUNG 3.037E-01 1. 686E- 01 1. 646E- 01 1. lOlE-01 GI-LLI 7.886E-03 8.009E-03 7.760E-03 7.458E-03 MAXIMUM ORGAN MAXIMUM AGEGROUP MAXIMUM DOSE BONE ADULT 9. 789E+OO 'j.. / 3 7 - I J - 4 / ;r1 r~

13~~

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4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A27 of A83

,C"~ *'-//?~I (30JU~ ~~ ~

TMINS UNIT 2 MST ATMOSPHERIC DOSE

SUMMARY

NOBLE GAS AIR DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359

~ ~ nefM ~ 1)/\L, ~ ~ ~ d_ ,,6;tti µ .* 9~ p /J h1S BA-.

GAMMA AIR DOSE: O.OOE+OO MR.EM AT 395 METERS IN SECTOR N BETA AIR DOSE: O.OOE+OO MR.EM AT 395 METERS IN SECTOR N 8506010000 TO 8506222359 PLUME DOSE:

TOTAL BODY: O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N SKIN PLUME: O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N

'MAXIMUM INDIVIDUAL DOSE TO: CHILD BONE l.02E+OO MR.EM AT 700 METERS IN SECTOR E

,~ tlcr3/4 . . ~, 7;2.E-1 d-Y./

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TMINS UNIT 2 LAST ATMOSPHERIC POPULATION DOSE

SUMMARY

RESULTS IN PERSON-rem 8506010000 TO 8506222359 PATH ORGANS BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI SKIN PLUME O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO GRND 2.6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 2.6E-02 3.0E-02 INHAL 5.0E-02 8.lE-03 2.2E-03 O.OE+OO 8.lE-03 3.6E-03 5.9E-05 2.2E-03

]YfTT ,K 2.3E-01 1. 9E-01 9.7E-02 O.OE+OO 6.2E-02 2.2E-02 4.2E-03 O.OE+OO 1 .r 3.5E-02 2.0E-02 1. 3E- 02 O.OE+OO 6.8E-03 2.4E-03 7.0E-04 O.OE+OO VEGET 1. 6E+OO 2.4E-01 4.5E-01 O.OE+OO 8.2E-02 2.8E-02 3.7E-02 O.OE+OO TOTAL 2.0E+OO 4.SE-01 5.9E-01 2.6E-02 1. SE- 01 8.lE-02 6.SE-02 3.2E-02 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A28 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: TOT BODY INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 2.97E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MREM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1. 23E- 02 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 6.63E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 7.49E-04 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 2.05E-0l MREM AT 720 METERS IN SECTOR E CHILD MEAT 7.45E-04 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 1.24E-02 MR.EM AT 1770 METERS IN SECTOR E

( "LD GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N CHILD TOTAL 2.72E-01 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 9.61E-04 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 1.37E-01 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 8.98E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 1.34E-02 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 2.06E-01 MREM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 9.54E-04 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 1. 22E- 01 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 1.84E-03 MREM AT 1770 METERS IN SECTOR E ADULT COW MILK 1.33E-02 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N

.t. ,LT TOTAL 1.92E-01 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A29 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: BONE INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 7.27E-03 MREM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MREM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1. 09E- 01 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.0OE+0O MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 1. 70E- 01 MREM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 1. SOE- 02 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 8.75E-01 MREM AT 720 METERS IN SECTOR E CHILD MEAT 3.97E-03 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 7.38E-02 MREM AT 1770 METERS IN SECTOR E

(' "LD GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N CHILD TOTAL 1.02E+O0 MREM AT 700 METERS IN SECTOR E TEEN PLUME O.00E+0O MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 2.26E-02 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION 5.0lE-01 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 2.53E-03 MREM AT 1770 METERS IN SECTOR E TEEN COW MILK 3.37E-02 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.0OE+0O MREM AT 0 METERS IN SECTOR N TEEN TOTAL 6.14E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.0OE+00 MREM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 2.14E-02 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 3.93E-01 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 3.49E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 2.02E-02 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.0OE+00 MR.EM AT 0 METERS IN SECTOR N i-. LT TOTAL 4.92E-01 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A30 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LIVER INFANT PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 1.30E-03 MREM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MREM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MREM AT 5310 METERS IN SECTOR N INFANT COW MILK 1.0SE-01 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N INFANT TOTAL 1.60E-01 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 2.97E-03 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 1.43E-01 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 2.22E-03 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 5.37E-02 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 2.SSE-01 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 3.76E-03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 8.39E-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 1. 68E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 3.l0E-02 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1. 74E- 01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 3.40E-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 5.42E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.08E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 1.76E-02 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N b.. .JLT TOTAL 1. 31E- 01 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A31 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: THYROID INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 5.37E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 0.00E+O0 MR.EM AT 1830 METERS IN SECTOR N CHILD VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N CHILD MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N CHILD COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N

( LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N TEEN MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N ADULT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N 1-~ .JLT TOTAL 5.37E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A32 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: KIDNEY INFANT PLUME 0.OOE+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 1. O0E- 03 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.O0E+0O MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.O0E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 2.BlE-02 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.O0E+00 MREM AT 0 METERS IN SECTOR N INFANT TOTAL 8.29E-02 MREM AT 700 METERS IN SECTOR E CHILD PLUME 0.O0E+00 MREM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 2.49E-03 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 4.67E-02 MREM AT 720 METERS IN SECTOR E CHILD MEAT 7.24E-04 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 1.75E-02 MREM AT 1770 METERS IN SECTOR E

( LD GOAT MILK 0.O0E+00 MREM AT 0 METERS IN SECTOR N CHILD TOTAL 1.21E-01 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.O0E+00 MREM AT 1830 METERS IN SECTOR N TEEN GROUND S.37E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 3.72E-03 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION 2.BBE-02 MREM AT 720 METERS IN SECTOR E TEEN MEAT 5.71E-04 MREM AT 1770 METERS IN SECTOR E TEEN COW MILK 1.05E-02 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.O0E+OO MREM AT 0 METERS IN SECTOR N TEEN TOTAL 9.74E-02 MREM AT 700 METERS IN SECTOR E ADULT PLUME O.0OE+00 MREM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 3.SlE-03 MREM AT 700 METERS IN SECTOR E ADULT VEGETATION 1.86E-02 MREM AT 720 METERS IN SECTOR E ADULT MEAT 7.0SE-04 MREM AT 1770 METERS IN SECTOR E ADULT COW MILK 5.96E-03 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.00E+O0 MREM AT 0 METERS IN SECTOR N j._ .,LT TOTAL 8.25E-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LUNG INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION l.26E-03 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK l.14E-02 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 6.64E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND S.37E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1. 94E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION l.67E-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 2.60E-04 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 6.30E-03 MR.EM AT 1770 METERS IN SECTOR E

( :LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 7.89E-02 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 2.16E-03 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION l.llE-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 2.22E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 4.l0E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 7.13E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION l.26E-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 6.09E-03 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.34E-04 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK l.98E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+0O MR.EM AT 0 METERS IN SECTOR N j._ .1LT TOTAL 6.33E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: GI-LLI INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 4.81E-06 MREM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 5.68E-04 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 5.43E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1.26E-05 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 1.07E-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 3.61E-05 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 5.74E-04 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 6.SlE-02 MREM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 2.83E-05 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 1.36E-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 5.96E-05 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 7.34E-04 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 6.81E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.37E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 2.69E-05 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 1.13E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 9.71E-05 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 5.54E-04 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N i-* .,LT TOTAL 6.57E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: SKIN INFANT PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N INFANT GROUND 6.27E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 2.97E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.00E+00 MREM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MREM AT 5310 METERS IN SECTOR N INFANT COW MILK 0.00E+00 MREM AT 5310 METERS IN SECTOR N INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 6.30E-02 MREM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 6.27E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 7.49E-04 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N CHILD MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N CHILD COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N

)LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 6.34E-02 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.O0E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 6.27E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 9.61E-04 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 0.0OE+00 MR.EM AT 2400 METERS IN SECTOR N TEEN MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 6.36E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 6.27E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 9.54E-04 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION O.00E+00 MR.EM AT 2400 METERS IN SECTOR N ADULT MEAT 0.0OE+00 MR.EM AT 5310 METERS IN SECTOR N ADULT COW MILK 0.0OE+00 MR.EM AT 5310 METERS IN SECTOR N ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N

,_ JLT TOTAL 6.36E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

BATCH FILES USED IN LAST CALCULATION INCLUDED IN THIS

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 92PDMSBA DATES:

8506010000 to 8506222359 NOTE:BATCH FILE LIST REPRESENTS CONTENT OF LAST CALCULATION RUN.

IF THE DATES OF SEPARATE RUNS (I.E. IND., POP., AIR) ARE NOT CONSISTENT, THESE BATCHES MAY NOT BE ALL INCLUSIVE.

4440-7380-90-017 Revision 2

.) .(o."J.:_ v~

//J111S , I 4440-7380-90-017 Revision 3 Attachment A Page A37 of A83 r~ iUj /J~, .4+f!J TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

NOBLE GAS AIR DOSE

SUMMARY

~-~-r- ~~ r VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359

,-k ~ ?Yb.5?. ~~,::-:-~~~~rd,: q;,rtJM£bR.

GAMMA AIR DOSE: O.OOE+OO MREM AT 395 METERS IN SECTOR N BETA AIR DOSE: O.OOE+OO MR.EM AT 395 METERS IN SECTOR N 8506010000 TO 8506222359 PLUME DOSE:

TOTAL BODY: O.OOE+OO MREM AT 1830 METERS IN SECTOR N SKIN PLUME: O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N MMCIM0M INDIVIDUAL DOSE .TOr: CHILD BONE i6.28E-01 :MR.EM.AT 700 METERS IN SECTOR E

-r;~ ~

1. t 71:- -1 ~r.,_ dll TMINS UNIT 2 LAST ATMOSPHERIC POPULATION DOSE

SUMMARY

RESULTS IN PERSON-rem 8506010000 TO 8506222359 PATH ORGANS BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI SKIN PLUME O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO GRND 1. 7E-02 1. 7E- 02 1. 7E- 02 1. 7E- 02 1. 7E- 02 1.7E-02 1. 7E- 02 1.9E-02 INHAL 3.6E-02 5.9E-03 1. SE- 03 O.OE+OO S.9E-03 2.5E-03 3.6E-05 1.SE-03 J" -,K 1.4E-01 1. 2E- 01 6.2E-02 O.OE+OO 4.0E-02 1.4E-02 2.7E-03 O.OE+OO

1. -~T 2.2E-02 1. 3E-02 8.2E-03 O.OE+OO 4.4E-03 1. 5E-03 4.3E-04 O.OE+OO VEGET 9.SE-01 1. GE- 01 2.SE-01 O.OE+OO 5.3E-02 1. 8E- 02 2.2E-02 O.OE+OO TOTAL 1.2E+OO 3.lE-01 3.6E-01 1. 7E- 02 1. 2E- 01 5.2E-02 4.2E-02 2.lE-02 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: TOT BODY INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 2.06E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 7.71E-03 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 4.25E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 5.20E-04 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 1. 24E-01 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 4.61E-04 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 7.78E-03 MR.EM AT 1770 METERS IN SECTOR E

( ;LD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 1. 67E-01 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 6.68E-04 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 8.36E-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 5.64E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 8.49E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1.28E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 6.62E-04 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 7.46E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 1.16E- 03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 8.49E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N 1-_ JLT TOTAL 1.19E-01 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A39 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE Sill-1MARY VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: BONE INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 5.16E-03 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 6.91E-02 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 1. 09E-01 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1.28E-02 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 5.31E-01 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 2.48E-03 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 4.67E-02 MR.EM AT 1770 METERS IN SECTOR E

( µD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 6.28E-01 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION l.62E-02 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 3.04E-01 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT l.57E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 2.12E-02 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 3.77E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION l.54E-02 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 2.38E-01 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.16E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 1.27E-02 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N 1-_ .LT TOTAL 3.02E-01 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LIVER INFANT PLUME 0.O0E+0O MREM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 9.35E-04 MREM AT 700 METERS IN SECTOR E

.INFANT VEGETATION 0.O0E+0O MREM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+0O MREM AT 5310 METERS IN SECTOR N INFANT COW MILK 6.74E-02 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+0O MREM AT 0 METERS IN SECTOR N INFANT TOTAL 1.03E-01 MREM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+0O MREM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 2.17E-03 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 9.17E-02 MREM AT 720 METERS IN SECTOR E CHILD MEAT 1.43E-03 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 3.45E-02 MREM AT 1770 METERS IN SECTOR E

( l.aD GOAT MILK 0.00E+0O MREM AT 0 METERS IN SECTOR N CHILD TOTAL 1. 64E- 01 MREM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+0O MREM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 2.75E-03 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION 5.40E-02 MREM AT 720 METERS IN SECTOR E TEEN MEAT 1.0BE-03 MREM AT 1770 METERS IN SECTOR E TEEN COW MILK 1.99E-02 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.O0E+00 MREM AT 0 METERS IN SECTOR N TEEN TOTAL 1.12E-01 MREM AT 700 METERS IN SECTOR E ADULT PLUME O.O0E+00 MREM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 2.49E-03 MREM AT 700 METERS IN SECTOR E ADULT VEGETATION 3.49E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 1.33E-03 MREM AT 1770 METERS IN SECTOR E ADULT COW MILK 1. 13E- 02 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.OOE+0O MR.EM AT 0 METERS IN SECTOR N 1-... .JLT TOTAL 8.4SE-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: THYROID INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 3.45E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N CHILD MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N CHILD COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N

( LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N TEEN MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN COW MILK 0.00E+00 MREM AT 5310 METERS IN SECTOR N TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 3.45E-02 MREM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N ADULT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N b.... JLT TOTAL 3.45E-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: KIDNEY INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 7.34E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1. 81E- 02 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 5.34E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 3.4SE-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1. 83E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 3.0lE-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 4.66E-04 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 1.13E-02 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N CHILD TOTAL 7.82E-02 :MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO :MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 2.73E-03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 1. 86E- 02 :MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 3.67E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 6.78E-03 :MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 6.30E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 2.SBE-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 1. 20E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 4.53E-04 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 3.83E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N b... .;LT TOTAL S.34E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LUNG INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 8.78E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 7.32E-03 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 4.27E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1.36E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 1. 07E-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 1.67E-04 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 4.05E-03 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 5.08E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 1. 52E- 03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 7.11E-03 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 1. 43E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 2.63E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 4.59E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 8.86E-04 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 3.91E-03 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 1. 51E-04 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 1. 27E- 03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N

.h__ JLT TOTAL 4.0SE-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: GI-LLI INFANT PLUME O.OOE+OO MREM AT 1830 METERS IN SECTOR N INFANT GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E INFANT INHALATION 2.92E-06 MREM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MREM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MREM AT 5310 METERS IN SECTOR N INFANT COW MILK 3.55E-04 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N INFANT TOTAL 3.49E-02 MREM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MREM AT 1830 METERS IN SECTOR N CHILD GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 7.67E-06 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 6.49E-03 MREM AT 720 METERS IN SECTOR E CHILD MEAT 2.23E-05 MREM AT 1770 METERS IN SECTOR E CHILD COW MILK 3.59E-04 MREM AT 1770 METERS IN SECTOR E 1LD GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N CHILD TOTAL 4.14E-02 MREM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MREM AT 1830 METERS IN SECTOR N TEEN GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 1.72E-05 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION 8.22E-03 MREM AT 720 METERS IN SECTOR E TEEN MEAT 3.68E-05 MREM AT 1770 METERS IN SECTOR E TEEN COW MILK 4.60E-04 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N TEEN TOTAL 4.33E-02 MREM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MREM AT 1830 METERS IN SECTOR N ADULT GROUND 3.45E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 1. 63E-05 MREM AT 700 METERS IN SECTOR E ADULT VEGETATION 6.85E-03 MREM AT 720 METERS IN SECTOR E ADULT MEAT 6.00E-05 MREM AT 1770 METERS IN SECTOR E ADULT COW MILK 3.47E-04 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N r- JLT TOTAL 4.lBE-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: SKIN INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 4.03E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 2.06E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK O.OOE+OO MREM AT 5310 METERS IN SECTOR N INFANT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N INFANT TOTAL 4.05E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 4.03E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 5.20E-04 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N CHILD MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N CHILD COW MILK O.OOE+OO MREM AT 5310 METERS IN SECTOR N LD GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N CHILD TOTAL 4.08E-02 MREM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 4.03E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 6.68E-04 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION O.OOE+OO MREM AT 2400 METERS IN SECTOR N TEEN MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N TEEN COW MILK O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 4.lOE-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 4.03E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 6.62E-04 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N ADULT MEAT O.OOE+OO MREM AT 5310 METERS IN SECTOR N ADULT COW MILK O.OOE+OO MREM AT 5310 METERS IN SECTOR N ADULT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N

., ___ JLT TOTAL 4.lOE-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

BATCH FILES USED IN LAST CALCULATION INCLUDED IN THIS

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 92PDMSDR DATES:

8506010000 to 8506222359 NOTE:BATCH FILE LIST REPRESENTS CONTENT OF LAST CALCULATION RUN.

IF THE DATES OF SEPARATE RUNS (I.E. IND., POP., AIR) ARE NOT CONSISTENT, THESE BATCHES MAY NOT BE ALL INCLUSIVE.

4440-7380-90-017 Revision 2

.Pllt115 ~ AR.

4440:7380-90-017~v1sion 3 ) Attachment A Page A47 of A83 7/J~ CJ~ M~~~

TMINS UNIT 2 LAST AlosPHERIC DOSE

SUMMARY

NOBLE GAS AIR DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359

~ ~"?TIIJf/4~~aNL:e4. .bf;.µ~ ~/4,,* 9.;i,cfr,*rL GAMMA AIR DOSE: O.OOE+OO l'-1REM AT 395 METERS IN SECTOR N BETA AIR DOSE: O.OOE+OO l'-1REM AT 395 METERS IN SECTOR N 8506010000 TO 8506222359 PLUME DOSE:

TOTAL BODY: O.OOE+OO l'-1REM AT 1830 METERS IN SECTOR N SKIN PLUME: O.OOE+OO l'-1REM AT 1830 METERS IN SECTOR N tMAX'IMUM INDIVIDUAL DOSE TO: ~HILD BONE 3.0lE+OO l'-1REM AT 700 METERS IN SECTOR E TMINS UNIT 2 LAST ATMOSPHERIC POPULATION DOSE

SUMMARY

RESULTS IN PERSON-rem 8506010000 TO 8506222359 PATH ORGANS BONE LIVER TOT BODY THYROID KIDNEY LUNG GILLI SKIN PLUME O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO GRND 2.8E-02 2.BE-02 2.8E-02 2.BE-02 2.BE-02 2.BE-02 2.BE-02 3.2E-02 INHAL ?.OE-02 ?.8E-03 3.5E-03 O.OE+OO 7.?E-03 5.BE-03 2.0E-04 3.5E-03 IY--,K 4.2E-01 2.0E-01 1. 5E-01 O.OE+OO 6.6E-02 2.3E-02 8.BE-03 O.OE+OO L ..T 8.2E-02 2.2E-02 2.5E-02 O.OE+OO 7.3E-03 2.6E-03 1. BE-03 O.OE+OO VEGET 5.3E+OO 2.6E-01 l.4E+OO O.OE+OO 8.?E-02 3.0E-02 1. 3E- 01 O.OE+OO TOTAL 6.0E+OO 5.lE-01 1. 6E+OO 2.BE-02 2.0E-01 8.9E-02 1. 6E-01 3.6E-02 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: TOT BODY INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND S.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 5.12E-04 MREM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MREM AT 5310 METERS IN SECTOR N INFANT COW MILK 2.58E-02 MREM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N INFANT TOTAL 8.39E-02 MREM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1.28E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 6.91E-01 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 1. 87E- 03 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 2.48E-02 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 7.77E-01 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION l.52E-03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 4.24E-01 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 1. 77E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 2.lOE-02 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 5.06E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 1.46E-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 3.53E-Ol MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 3.21E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 1. 89E- 02 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N j._ JLT TOTAL 4.34E-Ol MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A49 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE SDMMARY VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: BONE INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 1. 06E- 02 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1.66E-01 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 2.34E-01 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 2.62E-02 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 2.BOE+OO MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 8.47E-03 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 1.24E-01 MR.EM AT 1770 METERS IN SECTOR E

( LD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 3.0lE+OO MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.?6E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 3.12E-02 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 1.66E+OO MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 5.98E-03 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 6.30E-02 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1. 82E+OO MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND S.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 2.93E-02 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 1. 33E+OO MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 8.79E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 4.07E-02 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N 1-~ .,LT TOTAL 1. 46E+OO MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LIVER INFANT PLUME O.0OE+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 1.27E-03 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.0OE+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1.12E-01 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.O0E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 1.71E-01 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+0O MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 2.88E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 1.53E-01 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 2.38E-03 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 5.75E-02 MREM AT 1770 METERS IN SECTOR E

( .LD GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N CHILD TOTAL 2.73E-01 :MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 3.64E-03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 8.99E-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 1. 80E- 03 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 3.32E-02 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.O0E+0O MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1.86E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME O.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 3.29E-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 5.80E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.22E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 1.88E-02 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N

.L JLT TOTAL 1. 40E-01 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: THYROID INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT GOAT MILK 0.00E+00 MR.EM AT o METERS IN SECTOR N INFANT TOTAL 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 0.O0E+O0 MREM AT 1830 METERS IN SECTOR N CHILD VEGETATION 0.00E+00 MREM AT 2400 METERS IN SECTOR N CHILD MEAT 0.00E+00 MREM AT 5310 METERS IN SECTOR N CHILD COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N

( !LD GOAT MILK 0.O0E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 0.O0E+O0 MR.EM AT 1830 METERS IN SECTOR N TEEN VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N TEEN MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N TEEN GOAT MILK 0.00E+O0 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N ADULT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT COW MILK 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N

b. .,LT TOTAL 5.76E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: KIDNEY INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 9.66E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 3.0lE-02 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 8.87E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR-E CHILD INHALATION 2.40E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 5.00E-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 7.76E-04 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 1.88E-02 MR.EM AT 1770 METERS IN SECTOR E

,LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 1.30E-01 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 3.57E-03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 3.0SE-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 6.12E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 1.13E-02 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1. 04E-01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 3.37E-03 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 1.99E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 7.SSE-04 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK 6.39E-03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N i-. .JLT TOTAL 8.80E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

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SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: LUNG INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 2.19E-03 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK l . 22E-02 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 7.20E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MREM AT 700 METERS IN SECTOR E CHILD INHALATION 3.15E-03 MREM AT 700 METERS IN SECTOR E CHILD VEGETATION 1. 78E- 02 MREM AT 720 METERS IN SECTOR E CHILD MEAT 2.79E-04 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK 6.75E-03 MR.EM AT 1770 METERS IN SECTOR E

( )LD GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N CHILD TOTAL 8.56E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MREM AT 700 METERS IN SECTOR E TEEN INHALATION 3.SlE-03 MREM AT 700 METERS IN SECTOR E TEEN VEGETATION l.18E-02 MREM AT 720 METERS IN SECTOR E TEEN MEAT 2.38E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 4.39E-03 MREM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 7.76E-02 MREM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MREM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MREM AT 700 METERS IN SECTOR E ADULT INHALATION 2.0SE-03 MREM AT 700 METERS IN SECTOR E ADULT VEGETATION 6.52E-03 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.SlE-04 MREM AT 1770 METERS IN SECTOR E ADULT COW MILK 2.12E-03 MREM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MREM AT 0 METERS IN SECTOR N j._ .JLT TOTAL 6.BSE-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A54 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: GI-LLI INFANT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION l.61E-05 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION 0.00E+00 MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT 0.00E+00 MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK 1.22E-03 MR.EM AT 1770 METERS IN SECTOR E INFANT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 5.BBE-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 4.22E-05 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION 3.66E-02 MR.EM AT 720 METERS IN SECTOR E CHILD MEAT 9.55E-05 MR.EM AT 1770 METERS IN SECTOR E CHILD COW MILK l.23E-03 MR.EM AT 1770 METERS IN SECTOR E

( ',LD GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 9.55E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 9.41E-05 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION 4.61E-02 MR.EM AT 720 METERS IN SECTOR E TEEN MEAT 1.56E-04 MR.EM AT 1770 METERS IN SECTOR E TEEN COW MILK 1. 54E- 03 MR.EM AT 1770 METERS IN SECTOR E TEEN GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N TEEN TOTAL 1. 0SE- 01 MR.EM AT 700 METERS IN SECTOR E ADULT PLUME 0.00E+00 MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 5.76E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 8.90E-05 MR.EM AT 700 METERS IN SECTOR E ADULT VEGETATION 3.83E-02 MR.EM AT 720 METERS IN SECTOR E ADULT MEAT 2.S0E-04 MR.EM AT 1770 METERS IN SECTOR E ADULT COW MILK l.14E- 03 MR.EM AT 1770 METERS IN SECTOR E ADULT GOAT MILK 0.00E+00 MR.EM AT 0 METERS IN SECTOR N 1-,. .,LT TOTAL 9.73E-02 MR.EM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A55 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 8506010000 TO 8506222359 FOR: SKIN INFANT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N INFANT GROUND 6.72E-02 MR.EM AT 700 METERS IN SECTOR E INFANT INHALATION 5.12E-04 MR.EM AT 700 METERS IN SECTOR E INFANT VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N INFANT MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT COW MILK O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N INFANT GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N INFANT TOTAL 6.77E-02 MR.EM AT 700 METERS IN SECTOR E CHILD PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N CHILD GROUND 6.72E-02 MR.EM AT 700 METERS IN SECTOR E CHILD INHALATION 1.28E-03 MR.EM AT 700 METERS IN SECTOR E CHILD VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N CHILD MEAT O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N CHILD COW MILK O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N

( LD GOAT MILK O.OOE+OO MR.EM AT 0 METERS IN SECTOR N CHILD TOTAL 6.84E-02 MR.EM AT 700 METERS IN SECTOR E TEEN PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N TEEN GROUND 6.72E-02 MR.EM AT 700 METERS IN SECTOR E TEEN INHALATION 1. 52E- 03 MR.EM AT 700 METERS IN SECTOR E TEEN VEGETATION O.OOE+OO MR.EM AT 2400 METERS IN SECTOR N TEEN MEAT O.OOE+OO MREM AT 5310 METERS IN SECTOR N TEEN COW MILK O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N TEEN GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N TEEN TOTAL 6.87E-02 MREM AT 700 METERS IN SECTOR E ADULT PLUME O.OOE+OO MR.EM AT 1830 METERS IN SECTOR N ADULT GROUND 6.72E-02 MR.EM AT 700 METERS IN SECTOR E ADULT INHALATION 1. 46E-.03 MREM AT 700 METERS IN SECTOR E ADULT VEGETATION O.OOE+OO MREM AT 2400 METERS IN SECTOR N ADULT MEAT O.OOE+OO MREM AT 5310 METERS IN SECTOR N ADULT COW MILK O.OOE+OO MR.EM AT 5310 METERS IN SECTOR N ADULT GOAT MILK O.OOE+OO MREM AT 0 METERS IN SECTOR N b.. .,LT TOTAL 6.86E-02 MREM AT 700 METERS IN SECTOR E 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A56 of A83 TMINS UNIT 2 LAST ATMOSPHERIC DOSE SUl'-1MARY BATCH FILES USED IN LAST CALCULATION INCLUDED IN THIS

SUMMARY

VERSION: 92.0 PRINTED: 09-18-1992 92OPFIRE DATES:

8506010000 to 8506222359 NOTE:BATCH FILE LIST REPRESENTS CONTENT OF LAST CALCULATION RUN.

IF THE DATES OF SEPARATE RUNS (I.E. IND., POP., AIR) ARE NOT CONSISTENT, THESE BATCHES MAY NOT BE ALL INCLUSIVE.

4440-7380-90-017 Revision 2

ff l , _,_.,,;,,e 4440-7380-90-017 Revision 3 A Page A57 of A83 DATE:

THREE MILE ISLAND ENVIRONMENTAL CONTROLS Pos-f l>er,,el*t-_J 711,r,_,k,~-l S,:'br""~ eff/..,eJ..7 1 APPROVAL SHEET "'

4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A58 of A83 APPENDIX I DOSE CALCULATION WORKSHEET A. Mean River Flow (CFS) - contact York Haven River Flow B. Waste Dilution Factor (CFS) - NPDES Monthly Report: Main Discharge (gal*day- 1 to CFS conversion use l.55E-6)

c. FAR Field Dilution Factor (Drinking Water Hl Mixing Ratio)

. mean river flow waste dilution flow Near Field Dilution Factors (Shore Exposure #2, Fresh Water Sport Fish #3)

/ EG Clear Last and/or Total Files (Gaseous Individual, Population)

~EL Liquid Mixing Ratios, Clear Last and/or Total Files (Liquid Individual,Populat:

/

..-i:(ER Gaseous Release Paths: J;010 0 uJO

'4 EB,1Q Liquid and Gaseous source term inventories 1./ LD Calculate Liquid Pathway Individual Doses

_LLP Print Liquid Pathway Individual Doses

_Lpn Calculate Liquid Pathway Population Doses

/PA Print Liquid Pathway Population Doses

--iJ AI Clear Last and/or Total Air Dose (Gaseous)

- AA Calculate Air Doses

-AI Print Air Doses

_11'I Calculate Individual Gas Doses

_-LPI Print Individual Gas Doses

_/HY Calculate Maximum Exposed Receptor

_L1'P Calculate Population Gas Doses

_.!pp Print Population Gas Doses

/ DM Print Accumulated Dose Results HR Reset Program 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A59 of A83 3.4 0ffsite Dose Estimates Environmental doses for nonnal releases for cesium and strontium were quantified with the MIDAS code. This is the model used to estimate doses for quarterly reports to the NRC for TMI-2.

This model calculates the dispersion of radionuclides in three ways:

nonnal airborne dispersion (X/Q), depleted dispersion {which accounts for various removal processes like settling-out), and deposition (D/Q).

The MIDAS calculations use the "delta T", or the difference in temperature between sensors at 33 feet and 150 feet, of the onsite meteorological tower to detennine the atmospheric {Pasquill) stability class. The model then uses the stability class with other meteorological parameters such as wind speed and direction along with plant parameters including stack height, stack diameter, and stack flow rate to detennine the atmospheric dispersion.

The meteorological data used by MIDAS is automatically collected from the onsite tower and stored electronically for future use. Each meteorological tower sensor (there are about 20) is polled by a computer every 10 seconds.

The ten second results are averaged into a 15 mfoute average. The ff fteen .,

-~

minute averages ce,-..1;ev-,.'-t o,-.-C/..e. /..<:JU.- 4re vHI ~> f...tJu."1 **Ql~Pr, ;'I..<! ~ov,11 v*ivo ~ti!.CJsrJ., for r,~-1,i..e c~fcc,.ft1"tr",._r,, The calculations reported herein were based on one hour average meteorol ogi ca 1 data for the period January 1, 1985 to December 31, 1985. The calculation, therefore, is based on about yr((!() I -c--

different sets of meteorological conditions.

The accident dose calculations for the report were generated by selecting meteorological conditions which correspond to the worst case short-tenn dispersion characteristics. The TMI 0ffs1te Dose Calculation Manual X/Q value of 6.lE-4 sec/m 3 was used for this purpose.

To calculate the dose to the public, MIDAS employs numerous data files 16 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A60 of A83 which describe the area around TMI in tenns of population distribution and foodstuffs production. The area around TMI is subdivided into sixteen equal meteorological sectors (N, NNE, NE, ENE, E, ESE, etc.). Each sector is then r~presented in each set of data files and dispersion is calculated for each sector separately. Data files include such information as the distance from the plant vent to the site boundary in each sector, the population groupings, milk cows, milk goats, gardens of more than 500 square feet and meat animals.

MIDAS also contains dose conversion factors for 75 radionuclides for each of four age groups (adults, teenagers, children and infants), seven pathways (inhalation, ground deposition, plume direct dose, and ingestion of cow milk, goat milk, vegetables, and meats), eight organs (total body,* thyroid, liver, skin, kidney, lung, bone, and GI). The pathways, organs and age groups are those specified in Regulatory Guide 1.109.

The atmospheric dispersion is combined with the dose conversion factors and applied to each organ, age group, and pathway to estimate the dose to an individual by integrating by sector, distance, and time {meteorology changes) to detennine the dose, distance and direction to the maximum exposed individual.

The fi,ssion produtct $._0ur:,ce ter,ns _desert.bed in the previous section were

~ " ' " ' " " ' "'f/Jrlfl..e,rcq( ,"'Ci,v,ct'(,'t,.:( c:,,:r-cJ. I used to est,mat~ population doses with this methodology. The routine releases were averaged over one year, and were assumed to be released at a constant rate. Since the plant is assumed to be in a passive ventilation status for the majority of the time during IMS, the releases were treated as ground level releases for purposes* of estimating dispersion. This assumption results in conservative estimates of the degree of dispersi~n, compared to elevated release points. The assumption is appropriate even if the plant stack is the most likely path for releases because there will be essentially no exit velocity for the plume in the passive ventilation mode.

17 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachrpentt,e. F,~srvt- j).re1d11f01....&. Tr,.u.. fc!Q~~61:l,flf M/Nr.hT"-

'---.__

q _.. ~ 1,._ t;- f.,.:/,.ef!, 1 " r-J ,:, I' err-, I '1",r

The results of this cal cu lat ion are su11111arized in Table 4:V-:he total annual airborne pathway population dose is calculated to be "~'f/person-rem to the bone. The highest individual dose is estimated to occur at a distance

/

o.f about. 57JO ineters. A 0#,;rfJ/occupying this posit1on for a year would receive r

a maximum bone dose of .0.06 ~rem. ~

/..,,.,,cl. ,.o .,t'( 14,,~ de1s .. 1 ~u ,e e v,e fv<J. *kcl, u,; I -7 t1l I/),,,_ 1, /J ~s .,.rJ ""- '1'~ e Cf 'f .. .;/erJr

~"trG1.9!t. Sv$~"~(.o,.-1--q_, ~,.,e .... f'/r,*,.1-, *. /.Atq~f lt'd._,,;,t dOS(. cq{er.-/Qt,r;,-i cd1--s,dr,- -rl.,.,et part/... u..ayf: F,1( '".:l~s"'6-<1,-1 wcti-c.r '11J~F+: 1 cA.1 ee~ sl..tJv t:f,,..-e e.y,,/"".r;ci.,~ ~ "f"lc. e,.,f t- "'".Y'.,..~,

<t'Nf l=o(/1"' "'$~ J>rcJvf11 af- ~~I-toe, q .. t= rels<> cHr:J.. i1.t. ~~,,,..,v. . "-r11c-t'tc'ino,,td,n<-

ttJ Q#-. 1 r-d, .,,,Cl:C f ~ ~-,,:i "c f!J; "c :rl.., re.,..., 1o **nc 6 "',... e elf" a.1-.. q_ c1~ 'rt, I' l';~q; ,1., "1'/J/,:lt~,, *rl, ~

"r"t!'f(u-~-f,.,. ,i=1sf.. llz.rJC"'F{rr:,,._ /Jg*f!..':,'fJ.}/"'* l,,~ul~ fd/J.,.fa"t,,:,.._ .d~.SC, c01-$refc-vi rp({ U>f'"r ,,F, S"..,sff .. "to..,.,._u. £,u(..- "'--"{,:-.,.. ~'\L...,_~*7.. '""'"' o~ r~ :;z:.,vf_ ,£.~ l/'"frz1."t,f;',..&o..se ;s rr;.le~ /a,"f"V ~

'<:.,_ ~:Q1',- I"(".,._. *ii, 1'f~* 't~ ...~,

1

.: ,

I .I/,

The offsite doses from accidental re leases ot t1 ss,on products and trans-

"4ISO uranics were-Aevaluated using .. MIDASJ vs,,._, the emergency dose calculation routine used by Environmental Controls for calculating offsite doses for emergency planning purposes. The meteorological conditions for this case were chosen to produce a X/Q of 6.lE-4 which is normally used as the worst case accident X/Q for this type of evaluation. The accident calculations include only the inhalation dose pathway since it is expected that the other pathways tea" be restricted by protective actions under accident conditions. For this case, the maximum dose to an individual from fission products and transuranics is calculated to be 1-.'TJmrem to the bone. The transuranics contribute no more J r than about 'to 3/cc>f this tota 1

For comparison, the largest potential doses which could be postula~ed on the basis of the actual measurements of the Radiological Environmental Monitoring Program (REMP) for TMI (Units 1 and 2) are shown in Table 5 . for 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A62 of A83 Table 4 ESTIMATED DOSE COtllilMENTS RESULTING FROM ROUTINE AND ABNORMAL CONDITIONS DURING IMS I. POPUIATION DOSES Person-rem/yr.

Population doses from routine releases via airborne pathway:

Bone Dose Total Body Dose Population doses from routine releases via liquid pathway:

Bone Dose Total Body Dose Total population dose:

Bone Dose Total Body Dose II. DOSES TO MAXIMALLY EXPOSED INDIVIDUAL mrem/yr.

Dose from routine releases via airborne pathway:

Bone Dose Total Body Dose Dose from routine releases via liquid pathway:

~.()&~-

Bone Dose cl .cJe,1"~ /

Total Body Dose III. MXIIIJM ACCIDENTAL RELEASE kc ... c .......

Dose to maximally exposed individual from accidental release (bone dose limitin~) 't' 19 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 Attachment A Page A63 of A83 if any exist. These locations were primarily selected on the basis of where the highest predicted environmental concentrations would occur. While the indicator locations are typically within a few miles of the plant, the control stations are generally at least 10 miles from the plant. Therefore, control samples are collected at locations which should be unaffected by plant operations. They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation and radioactivity and fallout from prior nuclear weapon tests.

During 1985 there were over 2,000 samples taken from the aquatic, atmospheric, and terrestrial environments around THINS. More than 3,700 analyses were performed on these samples. Thirteen hundred and ttJrf):.y (1330) direct radiation dose measurements using TLDs were also made. Over 380 groundwater samples were collected and more than 1,000 analyses were performed on these samples. The collected samples show that operations at Three Mile Island during 1985 caused radiation doses to the public well below all applicable regulatory limits, and significantly less than doses received from other colllll'on sources of radiation.

Al though it is understood that the radionuclide inventories wi 11 be sub-stantially reduced during IMS, and the present mechanisms for transport and dispersal of residual activity (i.e.1 current cleanup operations) will be limited, no near-term changes to the TMI-2 Radiological Environmental Monitoring Program are anticipated.

4. OCCUPATIONAL PERSONNEL DOSES DURING IMS The PEIS concluded that the most significant environmental impact associated with the recovery operations will result from the radiation doses received by the work force. The above analysis of the off-site consequences associated 22 4440-7380-90-017 Revision 2

4440-7380-90-017 Revisio Water Resources Data 4440-7380-90-017 Rev3 Attachment A Pennsylvania Page A64 of A83 Water Year 1984 Volume 2. Susquehanna and Potom~c River Basins Volume 3.

Ohio River and St. Lawrence River Basins U.S. GEOLOGICAL SURVEY WATER-DATA REPORT PA-84-2 Prepared in cooperation with the Pennsylvania Department of Environmental Resources, the U.S. Army Corps of Engineers, Baltimore District, The Susquehanna River Basin Commission, and with other State, municipal, and Federal agencies 4440-7380-90-017 Revision 2

4440-7380-90-017 Revision 3 SUSQUEH~fMcRmm ,t(lASI N Page A65 of A83

.,,...* 01570500 SUSQUEHANNA RIVER AT HAR,RISBURG, PA 145

{National stream-quality accounting network, radiochemic&l and tritium program)

LOCATION.--Lat 40°15'17", long 76°53'11", D&uphin County, Hydrologic Unit 02050305, on east bank of City Island, 60 ft (18 m) downstream from Market Street Bridge, 3,670 ft (1,120 m) upstream from sanitary dam, in Harrisburg, and 1.7 mi (2,7 km) upstream from Paxton Creek. Water-quality sampling site 600 ft (183 m) upstream.

DRAINAGE AREA.--24,100 mi 2 (62,400 km'), approximately, WATER-DISCHARGE RECORDS PERIOD OF RECORD.--October 1890 to current year.

REVISED RECORDS.--WSP 711: 1929. WSP 1502; 1891-1923, 1926(M), 1928. WSP 1702: 1953 (total runoff in inches),

1958 (1957 calendar year mean discharge),

GAGE,--Water-stage recorder and concrete control. Datum of gage is 290,01 ft (88.395 m) National Geodetic Vertical Datum of 1929. Prior to Oct. 1, 1928, nonrecording gage at Walnut Street Bridge, 600 ft upstream, and oct. 1, 1928 to Aug. 31, 1975, water stage recorder at site 3,170 ft (966 m) downstream, all gages at same datum, REMARKS.--Records good except those for winter periods, wbich are fair. Flow slightly regulated by 15 flood-con-trol reservoirs, which have a combined capacity of 1,571,000 acre-ft (1,94 km"),

.---;? AVERAGE DISCHARGE ,_;ears, 34 ,460 ~ 9 7 6 m3 / s), 19 ,42 in/yr ( 493 mm/yr) .

EXTREMES FOR PERIOD OF RECORD.--Maximum discharge, 1,020,000 ft 3 /s (28,900 m1 /s) June 24, 1972, gage height, 32.57 ft (9,927 m), from floodmark; minimum, 1,600 ft 3 /s (45.3 m*/s) Nov. 29, 1930, result of freezeup. Minimum daily discharge since construction of sanitary dam and not affected by freezeup, 1,700 ft 3 /s (48.1 m'/s) Sept.

18, 1964; minimum gage height, 1.83 ft (0,558 m) Sept. 13, 1964.

EXTREMES OUTSIDE PERIOD OF RECORD.--Maximum stage known during period 1786 to 1890, 26.8 ft (8.17 m) at Walnut Street Bridge, June 2, 1889, discharge, 654,000 ft 1 /s (18,500 m3 /s).

EXTREMES FOR CURRENT YEAR.--Peak discharges above base of 180,000 ft'/s (5,100 m1 /s) and maximum (*):

Discharge Gage height Discharge Gage height Date Time (ft"/s) (m'/s) ( ft) (m) Date Time (ft 1 /s) (m'/s) ( ft) (m)

Dec. 15 0500 328000 9290 17 ,55 5.349 Apr. 7 0500 368000 10400 18.88 5.755 feb, 16 1100 *426000 12100 *20.74 6.322 May 31 0500 197000 5580 12.51 3.813 Minimum discharge, 3,260 ft 1 /s (92.3 m'/s) Oct. 9, gage height 2 ,95 ft (O .899 m),

DISCHARGE, IN CUBIC FEET PER SECOND, WATER YEAR OCTOBER 1983 TO SEPTEMBER 1984 MEAN VALUES DAY OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP 1 4250 5470 44400 27000 19200 54800 71200 50300 151000 34300 17300 13000 2 4180 5250 45200 26300 18300 48400 76600 46700 112000 49900 15100 12000 3 4000 50B0 40700 25000 18000 43700 80300 43100 84500 58500 13400 11400 4 3970 4870 37300 24600 19300 39500 89900 41600 66700 48500 13000 10800 5 4030 4890 38900 24900 25000 36200 133000 47500 55200 42600 13700 12100 6 3810 5420 41000 25000 27000 34200 284000 51900 46700 38600 14500 10B00 7 3730 5820 48900 24000 25000 33700 357000 55200 40100 39900 14600 10300 8 3750 5750 64800 23500 23000 33200 296000 53600 36100 56400 15900 10400 9 3480 5850 67100 21000 21000 32000 196000 51500 32800 65900 16600 10200 10 3470 6030 62500 19000 20000 29900 141000 51000 28800 55300 15000 9420 11 3710 7900 54000 18500 21500 27000 110000 52000 25800 43900 17800 8790 12 3970 11200 45900 16400 235o'o 25500 89600 51200 23400 38000 18800 8360 13 4250 13100 65800 13900 27000 23700 75200 48800 21000 34100 27600 8270 l4 4990 14200 251000 12900 35000 22900 65500 55900 19500 30500 42800 7870 15 5690 15800 321000 12000 299000 21900 60300 68300 18400 29200 53400 7980 l6 6070 16400 277000 12800 417000 23000 70800 78300 16900 25900 55900 7850 l7 6120 23200 201000 12700 352000 25500 87500 74000 17000 22600 52200 7690 18 7180 23600 138000 12100 258000 27400 95500 62400 23400 20100 44600 7510 19 8680 21100 97200 11600 205000 30100 97400 53100 52600 18500 35300 7660 20 7100 18700 74300 11100 181000 35700 92900 48000 80300 17800 31000 7940 2l 7910 20900 59100 10700 162000 38600 93100 47400 6B200 16500 29300 7610 22 7710 31100 50100 10000 140000 50800 89900 51400 55400 15400 26900 7260 23 7560 32800 45900 9600 113000 84000 77500 54100 43800 15800 24800 7030 24 8040 3iooo 42500 10000 94300 99900 67600 53400 37600 15200 21900 6740 25 8560 32400 25500 10800 82100 83300 62900 50100 36500 13900 20200 6490 26 8570 38800 21000 12600 70500 65300 66000 50400 35900 12800 18800 6270 27 8220 38000 21800 17000 62500 56800 78800 47300 35300 11900 17400 6080 2B 7390 35500 23000 22000 57700 52900 71900 42400 30500 11600 15800 6060.

29 6790 36700 30000 25000 59100 60500 59600 45300 26800 17400 14900 6100 30 6420 40000 29800 23000 65700 54400 132000 25800 17900 13400 6010 31 5830 26900 21000 67200 191000 19300 13800 TOTAL 179430 556830 2391600 546000 2876000 1373300 3291400 1849200 1348000 938200 745700 255990 MEAN 5788 18560 77150 17610 99170 44300 109700 59650 44930 30260 24050 8533 WAX 8680 40000 27000 417000 99900 357000 191000 151000 65900 55900 13000 MIN 321000 3470 4870 21000 9600 18000 21900 54400 41600 16900 11600 13000 6010 CPsu ,24 ,77 3,20 .73 4,11 1.84 4,55 2.48 1.86 1.26 .oo .35 IN, .40

.28 .BB 3.69 .84 4,44 2,12 5.08 2,85 2,08 1.45 1.15 CAL YR 1983 TOTAL 13197000 IIEAN 36160 MAX 321000 IIIN 3330 CFSl4 1.50 IN. 20.37 na YR 10a4 TOTAL 16351650 MEAN 44680 MAX 417000 MIN 3470 CFSM 1.85 IN. 25.24 4440-7380-90-017 Revision 2

.i,,.

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nn CLE,\R ~CESJNG COl'IPLETE ......

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.i:- ENTER, [Ml RELEASE POJNT 11-41 t

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ENTER, (NJ RELEASE POINT fl-4) l RET~NJ CO &AC,_ 10 PA£11JOUS OPTION I I ENTER,, {NNJ PATHWAY MJMBER 11-141 1, CRETUANJ CO BAClt TO PAEIIJOlJS OPTION RECEPTOR l RELEASE PT I PATHWAY MIXING RATIO l.32HE+82 ENTER, CN.Nl NEW VJ,LUE

/c RETURN l NO CHANGE 61 ENTER. LNNJ _ PAlHVAY NIJl'IBER 11-141

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CJ PS TANII. \IOLI.Jr1E UNJTS

_,,. RELEASE START/END DATE * . . . . . 861ftlliJll!l8 ,1 881231211111 ENTER, LCU l cuerc FEET RELEASE POINT I * * * * * * * * * * * : * * * * * * *

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ENTER. [~Rl10DAHRMNYRMODAHRMN1 SlART AND END DATES CD LR£TURN1 8690018186123124 COS~~ TO PREVIOUS OPlJON

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B0tl£. LIVER T.BODY THYRD ~IJIHEY LUNC GI-LLJ (0 11,'TER '?

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START DATE-861111 I I END DATE 86123124 ex, 0

BONE L IYEP T .BODY THVIID IUDNEY LUNC - CJ-LLJ c'o VATER 0 ADULT J.4E.::e I .DE-17 8.4E-1118 *-IE*N 8.8£-A 2.2£-ee Q, 7E-7 111.IE*N TEEN 2.&E-815 1.&E-1117 6.4E~**8.IE*H 6.3£-M 2.4E-N 7,2£-87 9.llf.+H ~

-.J CHIL.D 5. 3£-1115 3 .DE-87 I. 3£..;B!l 8.IE*N I. JE-87 4. !IE-1118 7. IE-87 111*.IIE*N ;a JNfANT 3.7E-ll!I 4.DE-1117 D.'5E-ll&:8.IE+II I.JE-87 5.JE-118 4.&E-87 1.IIE*IIII CD SNORE <

ADULT 6. 7E-1!7 6. 7E-llt7 6 ..7E-87 6. 7E-17 6. 7E-17 6. 7£-1117 8. 7E-llt7 7. DE-117 o*

TEEN J .. 8E- 6 3.&E-16 3.SE-118 3.8E-II& 3.8£-11& 3.8£-86 3.8E-IJ6 4.4E-N :::l CHJLJ) 7:DE-17 7.8£-1117 7.Cl£.,.87 7.laE-117 7.IIE-87. 7.DE-117 7.11£-87 8.2E-87 w lNF"NT B.1£*8B ll.8E*N 111 .. eE.*N a:IIE+N 6LIE+N"I.IIE*811 'lf;ll£+M 8:BE+l!III FV SPT FIStt ADa.T -4.6E-83 l. E-83 I.SE-83 I.SE.*N 4,6E-M 1..!IE.,;84 I. '!E-84 8.lft:*11111 TEEN 4.IIE-8'3 I .4E-81 1.2£-113 8ilE+81 4.8£-.. LIIE-84 1.IE-84 8.IIIE+H CHILD 4.BE-13 l.!E-IH 8.5E-B4 8*.eE*N 4:2£-84 1.15£-84 4.,3E-e5 8.IIE*U INf ANT lUi1E*88 11!1.IE*U 8.8E*81 IIU!E+H 8:8E*IIJ8 8.BE ....*:*S.IE** 8,_1£*N ENTER, tRET~Nl tONTINlJE,lSOl STAAT O~R.lE>ll E>CJT t

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BONE LlYEI' 1 .BODY THYIID ~IIINE.Y LI.MC CI-LLI ~IN TOTAL A!!Jl. T .6£-8'1 I .4£-83 1.BE-H 6. 7[-1117 4 .6£-liM 1.&E-84 I. 3£-84 7. IIE-17 TEEN . 1£-H 1.4£-113 1.2£-8'5 1.8E-N 4.QE-84 1.IIE-M I. IE-94 4. E-1&

CHILD .eE-8'1 l.!E-8'1 8.7E-IIM 7.0E-87 4.2£- l.flE-IM 4.!IE-11& a.2£-1117 JNF.U.l '3.7E-l!i 4.0E-87 D.5£-1116 11.IE+Blll 1.1£-87 !1.3£-18 4.6£-87 I.E*IIIO ENTER: lNl RECEPTOR NU'IBER n-s, lDl E'.1111 tRETURNl GO BM:lt 10 PREVIOUS OPTION J

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w STAJIT DATE 8611 I I END DATE 88121124 co 80fE LIVER T .BODY TlfYRD l(IIINEY LUNC CI-LLJ '?

co VATER .. . . _ 0 ADULT '3.4£-85 1.QE-17 8.4£-1118 1.IIE*D* 6.8£-88 2.2£-M* Q.7£-17 1.1£*1111 TEEN 2.&E-85 1.BE-87 6.4£-N 111.8£-.N 8.llE-* 2.4£-118 7.2£-1117 *a,8£*111111 ~

---i C.HILll 5.3£.-85 1.QE-87 1.'!E-11!5 I.IIE*U l.!E-17 4.91'.-a& 7.IE-17111':IE+II* :;o INFANT J;7E-8e' ... DE-87 D.eE.-18 l.aE N 1.JE-117 !LIE-118 4.&E-17 IIUIIE+N SHOl'E .. .

A.Dll.l 6.7£-17 6.7£-17 6.7E-lil7 6.7£-87 6.7£-17 6.7£-87 6.7£-17 7.QE-87 ~-

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TUN "S.8£-86 3.8E-86 '3.'ef:*16 3.8£-116 3.8E-8S 3.BE-1116 3.BE-16 4.4£-1116 o*

I CHJLJ) 7.GE-'-87 7.eE-87 7.lilE-1117 7.GE-117 7.IIE-17 7.0E-87 7.DE-87 D.2£-117 w INFANT llllilllE*eil e;eE*U Ill.SE** I.IE*IIS I.IE*- 11.K+N Ill.BE**: lll'ilE*N FV SPT FISH ADUl.1 4.&E-13 1.-4£-83 I.BE-83 111.ilE.*IIS 4.6E-84 1.5£-114 1.JE.-1114 1.BE*ll111 lEE.N 4.1£-83 1.4£-13 1.2£-113 8.IE+N 4.8E-84 t.GE-114 1.IIE-1114 8.IE+89 CtHlll :1£-83 1..3£-83 8.5£-IM lll.li1E*l8.*4.2E-&I 1.!5E-114.4.3E-li!l5 l.111£+111111 INFANT 8.IE+ll!l 8.IIIE*IIIII 11.lilE*U 8.IE*IS I.IE.all 8.8E*'-'!9'1.0 IE+1118 a*::_111£*H ENTER, LRETURNl C.ONTINllE.tSOl START OYER,lEXl EXIT

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START DAT£ 8818 I I END DATE 86123124 -I>

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4440-7380-90-017 Revision 3 Attachment B Page B1 of B2 EXELON TRANSMITTAL OF DESIGN INFORMATION

[8JSAFETY-RELA TED Originating Organization Tracking No. 5971-2019-002 NON-SAFETY-RELATED [8]Exelon REGULATORY RELATED Oother (S&L)

Station/Unit(s) Three Mile Island Unit 2 (TMl-2) Page 1 of 2 To: Harley Hutchins (S&L)

Subject:

TMl-2 Reactor Building Fire Dose Calculation Design Inputs Caitlin M. Keane Preparer 1l--:i~ ,r~7£_~

Preparers Signature I /31 I I q Date JA,_..ES.) 0yA,.t. /)_ !l f>w-- I /-=,1 / IC,,

Reviewer _/Revi~er's Signature Date r:" ~ ,, A.~- t,..... d:vUt-__ I /:?.I I /Cf Approver Approver's Signature Date Status of Information: [g!Approved for Use unverified Purpose of Issuance and

Description:

The purpose is to provide methodology approval and necessary design inputs for completion of Revision 3 of 4440-7380-90-017, PDMS SAR Section 8.2.5 Fire Analysis Source Terms.

Description of Information:

The information provided In this TOOi is as follows:

1. Source Terms

2. Chl/Q

3. Release Time

4. Additional Contamination

5. HEPA efficiency

6. Actinide Chemical Compound Source Documents (References):

1. GPU Nuclear Memorandum C312-92-1045, Dose Calculations

2. #87-008, Appendix I Dose Calculations

3. TMl-2 PDMS SAR

4. GPU Nuclear Memorandum C312-93-1015, TMl-2 RB Surface Contamination Activity

5. GEND-INF-075-PT-l, TMl-2 Core Debris Grab Samples - - Examination and Analysis Part 1 Distribution:

Caitlin Keane (Exelon)

Curtis Armer (Exelon)

Patrick Bennett (Exelon)

Jim Byrne (Exelon)

Anthony Klazura (S&L)

Larry Allen (S&L)

Harley Hutchins (S&L)

Page 1 of 2 Transmittal of Design Information

4440-7380-90-017 Revision 3 Attachment 8 Page 82 of 82 TRANSMITTAL OF DESIGN INFORMATION 1.0 Source Terms Total nuclide-specific activity released by a fire in the four reactor building areas are presented in Attachment 1 of GPU Nuclear Memorandum C312-92-1045, Dose Calculations (Attached). These are the source terms used in Revision 2 of the fire dose calculation (4440-7380-90-017) and should be the basis for calculating the revised source term to be used in Revision 3 of the analysis.

2.0 Chi/Q Calculation #87-008, Appendix I Dose Calculations (Attached), determines the bounding Chi/Q value for a release from the reactor building to be 7.67E-04 s/m 3

This is the value used in Revision 2 of 4440-7380-90-017 and should be used in Revision 3 of the analysis.

3.0 Release Time Consistent with discussion in the TMl-2 PDMS SAR and Revision 2 of 4440-7380-90-017, the release time to be used for the Case 2 (RB held at negative pressure) fire scenario is 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

4.0 Additional Contamination Additional contamination identified in the reactor building is not considered in Revision 2 of 4440-7380-90-017. It is presented in GPU Nuclear Memorandum C312-93-1015, TMl-2 RB Surface Contamination Activity (Attached). This additional contamination should be included in Revision 3 of the analysis.

5.0 HEPA Efficiency Revision 2 of 4440-7380-90-017 assumes a HEPA efficiency of 99%. This assumption should be used in Revision 3 of the analysis.

6.0 Actinide Chemical Compound Examination and analysis of the core debris recovered from TMl-2, GEND-INF-075-PT-1 (Page 105 of the Attached file), shows that the most likely chemical form of the actinides such as plutonium is the oxide form (PuO2). In Revision 3 of the analysis, it should be assumed that the plutonium particulates released by the fire are in the oxide form.

Page 2 of 2 Transmittal of Design Information

,

4440-7380-90-017 Revision 3 Attachment C Page C1 of C4

) . -.~,

[d ijl INuclear Memorandum

Subject:

TMI-2 RB Surface Contamination Date: April 5, 1993 Activity From: E. D. Schroll - TMI Licensing Engineer Location: SOB-1 .-*

,*~-.

~-f.:312~93~101Sir:

- *---* .. ~** ..*' .. *,; : ..

To: - J. 1. Byrne - Manager, TMI-2 Engineering

References:

. 1. GPU Nuclear calculation 6612-93-007, "Estimation of Surface Contamination in the TMI-2 RB," Rev. 0, March 1993.

2. GPU Nuclear calculation 4440-7380-9(}.017, "PDMS SAR Section 8.2.S Fire Analysis Source* Terms, 11 Rev. 2, July 1992.

The purpose of this memo is to document the impact of the Reference 1 surface contamination calculation on the Reference 2 fire analysis source term calculation and the subsequent offsite dose calculation. Based on the following, I have concluded that there is no impact on the Reference 2 calculation or the offsite dose calculation.

The TMI-2 Reactor Building (RB) is divided into four fire zones: 1) Reactor Building 305' and 347' elevations (OP); 2) "A" and "B" D-rings (ABD); 3) Fuel Transfer Canal (FTC); and 4). RB Basement (BAS). The FrC fire zone has been ignored since there will be no ignition source in that zone during Post-De-fueling Monitored Stomge (PDMS). For the other three zones, the PDMS fire calculation (Reference 2) assumed the following loose contamination values:

Cs-137 Sr-90 (Ci) (Ci)

OP 28,970 8,207 ABD 16,663 833 BAS 26,645 1,509 Surface Contamination Memo

~ ~. 4~0-7380-90-017 Revision 3 Attachment C Page C2 of C4

J. J. Byrne April 5, 1993 C312-93-1015 Page 2 The Reference I calculation reports the following (additional) surface contamination activity for those fire zones:

Cs-137 Sr-90 (Ci) (Ci)

OP <2 < 1:

ABD < 1 <1 BAS 645 592 Obviously, there is no impact on offsite dose from the calculated additional surface contamination in the OP and ABD fire zones. For the BAS zone, however, the activity is identified as being contained in the sediment. The Reference 2 fire calculation assumed that there were 459 Ci of Cs-137 and 446 Ci of Sr-90 in the sediment, i.e.,

differences from the Reference 1 values of+ 186 Ci of Cs-137 and +146 Ci of Sr-90.

These differences represent an increase of about 0.7% Cs-137 activity and 9.7% Sr-90 activity above the loose activity assumed in the fire calculation. Since these radionuclides contribute approximately 0.2 percent and 1 percent, respectively, to the calculated offsite dose of 13.5 mrem (Table 1), the above differences represent an increase of approximately .0002 Ilirem and .01 mrem, respectively.

Therefore, there is a negligible impact on the Reference 2 fire calculation from the excess surface oontamina1ion determined ~ c a k u l a l i o n .

E. D. Schrull Extension 8428 dlb cc: G. M. Lodde - Manager, Radiological Health R. E. Rogan - TMI Licensing Director E. J. Scheyder - Site Operations Director CARIRS-TMI Surface Contamination Memo

*j

. ,. ** 4440-7380-90-017 Revision 3 Attachment C Page C3 of C4 TABLE 1 EDS Source Tenn Estimate SOURCE TERM FOR BAS FIRE Airborne fuel 1 .47E*03 kg DOSE= 1.35E+01 mrem Fuel Amount Loose Airborne RB Released to (Ci/leg) of fuel Surface Suspension Airborne Environnent Atrborne Activity Factor (Ci) (Ci) Factor RG 1,109 (kg) (Ci) e= DCF (Chi/Q X DCF Dose Dose a b c d aXb+cXd e/100 (mrem/Ci) Usage F) (mrem/Ci) cmrem> <mrem>

Sr-90 6,45E+OO 1.47E*03 1.51E+01 1.0DE-03 2.46E-02 2.46E*04 3.50E+09 1.SSE-07 1.33E*01 Cs-137 7,81E+00 1.47E-03 2.66E+02 1.00E*03 2.781:-01 2.7BE*03 1.SSE-07 5.98E+07 2.SBE-02 Pu-238 2.54E*02 1.47E*03 O,OOE+OO 1.00E-03 3.73E*OS 3.73E-07 6,70E+12 1,SSE-07 3.88E*01 Pu-239 1.SSE-01 1.47E*03 O.OOE+OO 1.00E*D3 2.28E*D4 2.28E*06 7.5DE+12 1.SSE-07 2.65E+O0 Pu-240 7.57E*02 1.47E*03 O.DOE+OO 1,00E-03 1.11E*04 1.11E*06 7.SOE+12 1,SSE-07 1.29E+OO Pu*Z41 1.76E+OO 1.47E*03 0.00c+OO 1.00E*03 2.59E*03 2.59E-05 1.2.0E+11 1.SSE-07 4.81E*0t Am-241 2.61E*01 1.47E*03 O.OOE+OD 1.00E-03 3.84E*D4 3,84E*06 4.80E+12 1.SSE-07 2,85E+OD 7.8DE+OO 2.SBE-02 TOTAL DOSE 7.82E+OO X/Q MULT. 9.84E+00 1.37 HULT. 1 .3SE+01 This estimated calculation bas been verified by Mr. S. Acker, Environmental Controls, as being accurate within two significant figures.

Surface Contamination Memo

ML22105A092

Text

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4.0 REFERENCES

9.0 CONCLUSION

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