Text

Amergen/Exelon Calculation C-1302-822-E310-082, Rev. 0, Oyster Creek Analysis of Fuel Handling Accident Using Alternative Source Terms, Attachment 1
	ML073180407
Person / Time
Site:	Oyster Creek
Issue date:	10/05/2007
From:	Delarosa J; AmerGen Energy Co, Exelon Corp
To:	; Office of Nuclear Reactor Regulation
References
	C-1302-822-E310-082, Rev 0
	Download: ML073180407 (76)
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Enclosure 1 Description and Assessment Page 20 of 22 Attachment 1 AmerGen/Exelon Calculation C-1302-822-E310-082, Revision 0, "Oyster Creek Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms (AST)"

CALCULATION NO. C,1302-822-E310-082 NO. 0

.REV PAGE NO. I ATTACHMENT I Design Analysis Major Revision Cover Sheet Design Analysis (Major Revision) L Last Page No.- D-1 Analysis No.: 1 C-1302-822-E310-082 Revision: I 0

Title:

I Oyster Creek analysis of Fuel Handling Accident (FHA) using Alternative Source Terms (AST)

EC/ECR No.:" 07 - 0 o7qO Revision: ' 0 Station(s): ' Oyster Creek Component(s): _

Unit No.:' t N/A Discipline:' M Descrip. Code/Keyword: " Dose Safety/QA Class:" S System Code: ' 822 Structure: "1 NIA CONTROLLED DOCUMENT REFERENCES "

Document No.: From/To Document No.: From/To C-1 302-826-E310-018 Rev. 0 From From C-13302-226-E620-369 Rev. 0 From From C. 1302-226-E620-369 Rev. 0 From From C-1302-826-E540-017 Rev. 3 From Is this Design Analysis Safeguards Information? Yes El No 0 If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Yes I No 0 It yes, ATI/AR#:

Assumptions? "

This Design Analysis None - Oiginal Issue In its entirety.

SUPERCEDES: Ns Description of Revision (list affected pages for partials): '"ORIGINAL ISSUE REV. 0 Preparer: Jessica DeLaRosa 4

\5/50 7 Prim Naie~Inffu Dt Method of Review: Detailed Review 0 Alternate Calc lions (attached) 0 Testing 0 Reviewer:" Thomas J. MscIsz / 6 plnnl Naffe DM Review Independent review 0 Peer review 0 No tes: " JTn, , t-r4-Zv - 1 -

(Far E -,,M A, .eset " I...

External Approver: NIA P,iraNae sign ft"e DOW Exelon Reviewer:"

pli N&ne SignNW*e Dam Independent 3 td Party Review Reqd? Yes 0 No I WGI peroped ITPR ExeIon Approver:- 5 Rl 7-'s- . ,, /-/

Fr.,, Nome*~SNm .

I CALCULATION NO. C-1302-822-E310-082 I REV. NO. 0 1 PAGE NO. 2 1 General Review Questions Page 1 of 1 DESIGN ANALYSIS NO. C-1302-822-E310-082 REV: 0 Yes No N/A

1. Does the Design Analysis conform to design requirements? 0] El

2. Does the Design Analysis conform to applicable codes, standards, and El regulatory requirements?

3. Have applicable design and safety limits been identified? 0] El

4. Is the analysis method appropriate? 0] El

5. Are the methods used and recommendations given conservative relative to 0] El the design and safety limits?

6. Are assumptions/Engineering Judgments explained and appropriate? 0] El El

7. Have appropriately verified Computer Program and versions been 0] E] El identified, when applicable? El

8. Does the Computer Program conform with the NRC SER or similar 0] El El El document when applicable?

9. Has the input been correctly incorporated into the Design Analysis? 0]

10. Has the input been reviewed by all cognizant design authorities? 0]

El

11. Are the analysis outputs and conclusions reasonable compared to the 0]

inputs and assumptions?

12. Are the recommendations/results/conclusions reasonable based on previous experience? 0 El El

13. Has a verification of the Design Analysis been performed by alternate methods? [.in-depe~ndent run of sa~cme puter prga. El El

14. Has all input data been used correctly and is it traceable? 0] El El

15. Has the effect on plant drawings, procedures, databases, and/or plant 0] El simulator been addressed? El El

16. Has the effect on other systems been addressed? 0] El E]

17. Have any changes in other controlled documents (e.g. UFSAR, Technical 0] El Specifications, COLR, etc.) been identified and tracked?

18. When applicable, are the analysis results consistent with the proposed license amendment? 0 El El 19.' Have other documents that have used the calculation as input been reviewed and revised as appropriate?

20. Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change? [No othe' E] El 0 D~esign Analyses affected]

21. Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or analysis methodology are based on an out-of-date methodology or 0 El El code, additional reconciliation may be required if the site has since committed to a more recent code)

22. Have supporting technical documents and references been reviewed when necessary? ED El El

I-CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGENO.2 Table of Contents DESIGN ANALYSIS COVER SHEET ................................................................................................ .......

GENERAL REVIEW CHECKLIST FOR DESIGN ANALYSIS ....................................................................... 1.1 TABLE OF CONTENTS ...... ........................ ..... 2

1. P U RP OSE /O B JEC TIV E .................................................................................................................................. 3

2. METHOD OF ANALYSIS AND ACCEPTANCE CRITERIA ............................ 4 2 .1. F uel S o urce T erm M odel ............................................................................................................................. 4 2 .2 . Gap A ctiv ity ........ .......................................................................................................................................... 4 2.3. Pool Decontamination Factor (DF) ....................................................................................................... 5 2 .4 . R elease M o d el ............................................................................................................................................... 5 2 .5 . C ontro l Room M odel ................................................................................................................................... 6 2 .6 . D o se M o d elin g .............................................................................................................................................. 7 2 .6 . 1. EA B an d LP Z ........................................................................................................................................... 7 2 .6 .2 . C o n tro l Ro o m ........................................................................................................................................... 7 2 .7 . A ccep tance C riteria ..................................................................................................................................... 7

3. A S S U M P T ION S ............................................................................................................................................... 9

4. D E S IGN IN P U T .............................................................................................................................................. 10

5. R E F ER EN C E S ................................................................................................................................................ 13

6. C A LC U LA T ION S .......................................................................................................................................... 14 6.1.1. RADTRAD Run Compartment Information ........................................................................................ 14 6.1.2. RADTRAD Run Transfer Pathway Information ................................................................................. 15 6.1.3. RADTRAD Run Dose Location Information ...................................................................................... 15 6.1.4. RADTRAD Run Source Term & Dose Conversion Factor Information .............................................. 15

7. RESULTS AND CONCLUSIONS ....................................................... )................................................... 17 Attachments A. RADTRAD Dose Conversion Factor Input File B. RADTRAD Output C. FHA RADTRAD Nuclide Information File D. FHA RADTRAD Release Fraction and Timing File

I CALCULATION NO. C-1302-822-E310-082 IREV. No. 0 1 PAGE NO.3

1. PURPOSE/OBJECTIVE The purpose of this calculation is to apply Alternative Source Term (AST) methodology to the analysis of the design basis Fuel Handling Accident (FHA) for Oyster Creek Nuclear Generating Station. Dose consequences are calculated at the Exclusion Area Boundary (EAB), the Low Population Zone (LPZ) and the Control Room (CR). This calculation determines the safety features required to assure that regulatory limits in 10CFR50.67 are met, and is performed in conformance with guidance for analysis of this event provided in Regulatory Guide (RG) 1.183.

This accident analysis evaluates the movement of fuel that has decayed a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months since it last occupied part of a critical reactor core.

Guidance in Technical Specification Task Force (TSTF) Traveler 51 suggests that a "recently irradiated fuel" parameter be developed to identify when secondary containment integrity features are required for spent fuel movement. In this calculation, recently irradiated fuel would be that which requires one or more of the following safety features:

1. Secondary Containment Integrity to assure that releases are through the plant ventilation stack.

2. The Standby Gas Treatment System (SGTS) for secondary containment release treatment.

This calculation supports changes to the OCNGS Technical Specifications that consider maintenance and operability of the secondary containment and emergency filtration systems and subsystems previously required to mitigate the radiological consequences of fuel handling accidents may not be necessary. Not having to consider secondary containment and control room integrity and filtration requirements in support of refueling activities has the potential to improve the flexibility and duration of scheduled plant outage activities.

RG 1.183 (Ref. 2) is the basis for these evaluations. Concerning the FHA, this AST guidance has the advantage of smaller gap fractions, a larger spent fuel pool decontamination factor [DF], and dose criteria that replace both the whole body and thyroid dose limits with a limit on Total Effective Dose Equivalent [TEDE].

The other changes from the current UFSAR analysis are listed below.

" An offsite dose limit of 6.3 rem TEDE (RG 1.183 & 10 CFR 50.67(b)(2)(i)) is applied instead of the Standard Review Plan (SRP) 15.7.4 values of 25% of the 10CFR100 limits.

" A control room dose limit of 5 rem TEDE (RG 1.183 & 10 CFR 50.67(b)(2)(iii)) is applied instead of the 5 rem whole body, or its equivalent (10CFR 50, Appendix A, GDC-19).

Design Basis analysis is based on NRC RG 1.183.

The Control Room x/Q'S were recalculated for release from various potential release points with the new limiting x/Q's applied to this analysis. A ground level release model is used.

No credit is taken for Secondary Containment automatic isolation and filtration

Dose Conversion Factors (DCFs) for Immersion and Inhalation are taken from Federal Guidance Reports (FGRs) 12 (Ref. 5) and 11 (Ref. 4), respectively. RG 1.183 cites these DCFs as acceptable current estimates for evaluating the radiological impact of nuclear plant accidents.

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO.4 ý

2. METHOD OF ANALYSIS AND ACCEPTANCE CRITERIA Analyses of radiological consequences resulting from a design basis Fuel Handling Accident (FHA) are performed using the guidance for application of Alternative Source Terms to this event in RG 1.183.

Analyses of radiation transport and dose assessment are performed using RADTRAD v. 3.03 (Exelon DTSQA EX0004754). RADTRAD is a simplified model of RADionuclide Transport and Removal And Dose Estimation developed for the NRC and endorsed by the NRC as an acceptable methodology for reanalysis of the radiological consequences of design basis accidents. The technical basis for the RADTRAD code is documented in section 2 NUREG/CR-6604 (Ref. 3). The methodologies significant to this analysis are the dose consequence analysis (NUREG Section 2.3) and the Radioactive Decay Calculations (NUREG Section 2.4).

2.1. Fuel Source Term Model The source term nuclide inventory (Ref 10) used for the Fuel Handling Accident (FHA) is the same as that previously used in the LOCA AST analysis (Ref 11). This inventory is considered to be bounding with respect to expected fuel types in use at OCNGS.

Regulatory Guidance for DBA fuel handling accidents is such that the fission product inventory of each of the damaged fuel rods is determined by dividing the total core inventory by the number of fuel rods in the core. To account for differences in power level across the core, radial peaking factors are applied in determining the inventory of the worst-case damaged rods.

For OCNGS, the fraction of the core fuel damaged is based on the GESTAR II limiting case of damaging 140 fuel pins (based on a "Heavy Mast" design; i.e., the "NF500 mast") from GEl 1 or GE13 9x9 fuel bundle arrays with the analyzed equivalent of 74 pins per bundle, and with all of the damaged fuel assumed to have a limiting Radial Peaking Factor (PF) of 1.7. This analysis is for an assembly and mast drop from the maximum height allowed by the refueling platform over the reactor well onto fuel in the reactor, and bounds all locations in terms of fuel damage potential.

OCNGS core loads consist of all GEl 1 9x9 fuel assemblies, and therefore, the results of the GESTAR II limiting case are consistent with OCNGS core loading. Fuel in the spent fuel pool has sufficient water coverage (>23 feet) over top of active fuel.

A 'B C D E Damaged Core Fraction Assumning Core is All Radial Damaged Core Fraction Fuel Pins in; Failed Specified. Bun~dle Type Peaking with PF Bundle Type Array Buniidle. 'Pins [C=B /(560*A)i Factor,(PF) ICD GEl 1, GEl3 9x9 74 140 0.003378 1.7 0.005743 Various 8x8 62 124 0.003571 1.5 0.005356 Various 7x7 49 111 0.004045 1.5 0.006068 With a 1.7 radial peaking factor, the associated power of the damaged fuel = 1969 MWth

0.003378

1.7 = 11.31 MWth.

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGENO.5 Because of radioactivity decay, the worst-case fuel handling accident is that associated with handling fuel that has recently been part of a critical core operating at full power immediately prior to the accident. Movement of irradiated fuel will not occur less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the associated reactor shutdown, and therefore, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is the minimum decay period assumed. This value continues to be a very conservative assumption for BWRs, given the extensive operations necessary associated with reactor disassembly before commencing fuel movement. Radioactive decay from the time of shutdown is modeled for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to support the opening of the most restrictive secondary containment potential release point.

2.2. Gap Activity This calculation is applicable to fuel whose burnup and power limits are bounded by those specified in RG 1.183, footnote 11. This allows application of the gap activity fractions for LOCA events per RG 1.183, Table 3, which are as follows:

5% of the noble gases (excluding Kr-85) 10% of the Kr-85 5% of the iodine inventory (excluding !-131) 8% of the 1-131 12% of the Alkali metal inventory Because RADTRAD does not allow for application of isotope specific release fractions, the "ocfhaikr.nif" file is modified to accommodate the differential gap activities among the halogen (I-131) and noble gas (Kr-85) gap fractions dictated by RG 1.183 (Ref. 2) shown above. Therefore, the initial activity of isotope 1-131 and Kr-85 are multiplied by 1.6 and 2.0, respectively, in order to accommodate the respective 8% and 10% release fractions directed by regulatory guidance (Ref.

2).

2.3. Pool DecontaminationFactor(DF)

An assessment of water coverage and effective DFs considering FHAs over the reactor well and in the spent fuel pool was performed. It identified that the drop over the reactor well is more limiting.

Water coverage over the reactor well is -30 feet. However, no additional credit is taken for water depth greater than 23 feet in order to maintain conservatism and consistency with regulatory guidance.

For a drop over the spent fuel pool, coverage over the dropped assemblies is slightly less than 23 feet, assuming that the dropped bundle is laying across the tops of fuel bundles within the spent fuel racks. There is always greater than 23 feet of water above top of active fuel for bundles within the racks. However, the slight reduction in DF due to slightly less than 23 feet water coverage is offset by the reduction in fuel damage due to a much shorter drop (i.e., less than approximately 4 feet) over fuel in the spent fuel pool.

2.4. Release Model Release modeling uses the RADTRAD computer program. The compartments are the Refuel Floor Air Space (in the Reactor Building), the Environment (EAB and LPZ), and the Control Room.

CALCULATION NO. C-1 302-822-E310-082 REV. No. 0 PAGE NO. 6 The refuel floor exhaust rate is set artificially high at 6 air changes per hour. This results in 99.9999% of the contained radioactivity being exhausted within two hours.

The RFT files for this event provides for a rapid release (1.0E-04 hours) of gap activity to the fuel pool. The nominal gap fraction for noble gas is 5%, and for iodine is also 5%. The iodine release is further reduced to reflect the pool DF of 200. As discussed above, the normal Nuclide Inventory File (NIF) representing a OCNGS core is artificially adjusted to account for the higher than average gap fractions for 1-131 and Kr-85 provided by RG 1.183.

The compartments are the Refuel Floor Air Space, the Environment, and the Control Room. Since the release of activity from the Refuel Floor Air Space is a time-dependent function only (all activity is assumed to be released over a two hour period), the actual volume is independent of the release. Therefore, an artificial volume of 100 ft 3 was chosen for simplicity. The activity in the volume after a period of time can be expressed using the standard activity decay equation A=A 0e-At, where, in this case, A = initial activity, A0 = final activity, X = the fractional release rate, and t = 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release duration. Assuming that the fraction of activity remaining in the Refuel Floor Air Space after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (A/A0 ) is sufficiently small (e.g., 0.0001), solving the equation for A yields a value of 4.605/hr (7.65 ft3/min based on an assumed volume of 100 ft 3). Therefore, setting the Reactor Building exhaust rate to an artificially high value (i.e., >0.0765 ft3/min) will assure essentially complete release within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .'

This accident analysis evaluates the movement of fuel that has decayed a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months since it occupied part of a critical reactor core. Since release through the plant vent stack is not assumed, the release is treated as a ground level (rather than elevated) release. No SGTS filtration is credited.

2.5. Control Room Model The Oyster Creek Control Room HVAC system contains no HEPA or Charcoal filters. All intake air into the control room is unfiltered. There is no recirculation of CR air. As a result, the radionuclide concentration inside the control room reaches equilibrium with the concentration of the plume at the Control Room HVAC System air intake within a short period of time after the postulated release. Equilibrium occurs whether the ventilation system was in purge or partial recirculation mode of operation. In the purge mode (14,000 cfm system flow) the control room volume is-changed once every 2 minutes. In the partial recirculation mode (2,000 cfm system intake flow) the control room volume is changed once every 14 minutes. It would require only one hour for the control room to be at radiological equilibrium with the outside environment while in the partial recirculation mode. The dose to control room operators is calculated over a total duration of 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months . Oyster Creek LAR No. 315, "Application of Alternative Source Term, submitted to NRC on March 28, 2005 (21 30-05-20040), reanalyzed the design basis LOCA radiological dose consequences for Oyster Creek using Alternative Source Term methodology. The control room operator dose consequences are conservatively analyzed using the full Control Room HVAC System flow seen during the purge mode of operation. It should be noted that the purge mode (14,000 cfm intake) is not expected to be in operation during a radiological event. Therefore, the assumption that the Control Room HVAC system is operating in the purge mode for the duration of the FHA results in a conservative radiological dose to control room operators. In both modes of operation (purge and partial recirculation) the radiation exposure to personnel in the control room remains within the regulatory limits. Rather, it would be in the partial recirculation mode (2,000 cfm), which produces a slightly lower dose. The sensitivity study bounds the range of flow between the 2,000 cfm minimum flow in the partial recirculation mode, and the maximum flow of approximately 30,000 cfm for the unlikely event both fans are operating in the full purge mode.

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. 7 Therefore, since any increase in flow beyond 4,000 cfm does not cause an increase in dose, the amount of unfiltered inleakage does not affect the total calculated control room operator dose (calculated at 14,000 cfm). Note that this has previously been approved for TS Amendment No.

262 dated April 26, 2007.

2.6. Dose Modeling Dose models for both onsite and offsite are simplified and meet RG 1.183 requirements. Dose conversion factors are based on Federal Guidance Reports 11 and 12 (Ref. 4, 5). RADTRAD uses the following formulations, integrated numerically over the accident duration:

2.6.1. EAB and LPZ Doses at the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) for the FHA are based on the following formulas:

DoseCEDE (rem) = Release (Curies) *-(sec/m )

Breathing Rate (m 3 /sec)

Inhalation DCF (remCEDE/Ci inhaled)

Q and Dose EDE (rem) = Release (Curies) *- (sec/m 3 )

Submersion DCF (rem EDE - im 3

/Ci - sec)

I Q and finally, DoseTEDE (rem) = DoSeCEDE (rem) + DoseEDE(rem) 2.6.2. Control Room The formulas used by RADTRAD, by time increment, are:

DoseCEDE (rem) = Time Dependent CR Air Concentration (Ci/m 3 )

Time Increment Duration (sec)*

Breathing Rate (m 3 /sec)

Inhalation DCF (remCEDE /Ci inhaled)

Occupancy Factor of 1 and Dose EDE (rem) = Time Dependent CR Air Concentration (Ci/m 3 )

Time Increment Duration (sec)*

Submersion DCF (rem EDE -im3 /Ci - sec)

Occupancy Factor of 1* CR Geometry Factor and finally, DoseTEDE (rem) = DosecEDE (rem) + DoseEDE(rem) 2.7. Acceptance Criteria Dose acceptance criteria are per 10CFR50.67 and RG 1.183 guidance.

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGENO.8 Table 1 lists the regulatory limits for accidental dose to 1) a control room operator, 2) a person at the EAB, and 3) a person at the LPZ boundary.

Table 1.

Regulatory Dose Limits (Rem TEDE)*

CR EAB LPZ (30 days) (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) (30 days 5 6.3 6.3

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO.9

3. ASSUMPTIONS Assumptions and bounding analyzed conditions regarding the fuel handling accident scenarios are provided below.

1. Movement of recently irradiated fuel will not occur less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the fuel has occupied a critical reactor core. This establishes the basis for a definition of "recently irradiated fuel".

2. Fuel bundle peak burnup will not exceed the limits of RG 1.183 footnotes10.

3. For fuel exceeding a 54 GWD/MTU burnup, the maximum linear heat generation rate will not exceed the RG 1.183 footnote 11 limit of 6.3 kW/ft rod average power.

4. The design basis GESTAR II bounding fuel damage assessment scenario associated with a drop over the reactor core is used. For this event the RG 1.183 DF value of 200 is conservative.

5. Spent fuel source terms are based on reactor core source terms as used in the AST LOCA analysis previously reviewed and approved by the NRC in TS Amendment No. 262 dated April 26, 2007.

6. The damaged fuel is assumed to have operated at a radial peaking factor of 1.7.

7. Activity reaching the refuel floor airspace will essentially all be exhausted within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by using an artificially high exhaust rate. This also provides an allowance for uneven mixing in the refuel floor airspace.

8. The release pathway is unfiltered at ground level to the Control Room normal intake(s).

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. 10

4. DESIGN INPUT The design inputs used for this calculation are summarized in the following table:

Parameter or:-Method 'AST Value Commirents Reactor Power 1969 MWth Includes 2 % margin for instrument uncertainty relative to the rated thermal power of 1930 MWt.

Fuel Assembly Configuration 9 x 9 with 140 rods damaged Bounding assumptions for and properties current Oyster Creek licensing basis FHA. Movement of irradiated fuel will not occur less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the associated reactor shutdown.

Radial Peaking Factor 1.7 Conservative bounding assumption Allowable Fuel Burnup and RG 1.183, Table 3. The GE 11 fuel burnup is 27.6 non-LOCA gap fractions Fuel bundle peak burnup will GWD/MTU. Therefore, the. 6.3 not exceed 62 GWD/MTU. For kW/ft linear heat generation fuel exceeding 54 GWD/MTU, rate limit does not apply.

the maximum linear heat generation rate will not exceed 6.3 kW/ft.

FHA Radionuclide Inventory From the 60 isotopes forming Spent fuel source terms are the RADTRAD library used in based on the same bounding the LOCA analysis, with decay reactor core source terms as to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Gap activities are was used for the LOCA per R.G. 1.183. analysis.

Underwater Decontamination Noble Gases: 1 For conservatism, the effective Factor minimum depth of 23 feet is Particulate (cesiums and assumed to be the water rubidiums): infinity coverage over the reactor core. This is the worst-case Iodine: 200, corresponding to location for a fuel drop FHA to a 23-ft water depth for an take place (significantly more assembly drop into the reactor damage is produced than a vessel drop in the fuel pool).

Iodine chemical distribution From RG 1.183 95% CsI, instantaneously dissociating in the pool water and re-evolving as elemental iodine. Since the pH of the pool water is not maintained above,7, iodine is assumed to be 97% elemental and 3%

organic in the air space above the pool.

Activity Transport to the Activity reaching the refuel This also provides an Environment floor airspace will essentially allowance for uneven mixing in be all exhausted within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months the refuel floor airspace.

by using an artificially high exhaust rate.

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. 11 I Parameterior Method-, ..AST:Value Comments Release Pathways The release pathways are No credit is taken for filtration described in Table 4-1. by the SGTS, or the elevated release resulting from exhaust through the Oyster Creek Main Stack.

Dose Conversion Factors EPA Federal Guidance Reports 11 and 12 Offsite Dose Limit 6.3 rem TEDE After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 10CFR50.67 and RG 1.183 Control Room Dose Limit 5 rem TEDE for the duration of Per 10CFR50 App. A, GDC 19 the accident and 10CFR50.67 CR Volume Volume 27,500 ft4 As previously demonstrated for the LOCA analysis, the CR CR Intake Rate 14,000 cfm dose is maximized when an intake rate of 4,000 cfm is achieved. However, the maximum intake of 14,000 cfm in the purge mode is used for conservatism. This also eliminates the need to address the unfiltered inleakage rate, since additional intake produces no additional dose.

Refuel Floor Ventilation Rate For this analysis, an artificial This evacuates 99.9999% of and Volume volume of 100 ft 3 with an all activity within 2-hours.

artificially high exhaust rate is I assumed for simplicity.

I.CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. 12 1

- Parameter or Method. AST Value Comments CR Potential Release Points Limiting X/Qs (0 - 2 hr) From Calculation C-1302-822-3 E310-081, Revision 0. All Drywell Access Facility (West 1.61 E-03 sec/mi releases considered as ground Wall) level releases.

3 Drywell Access facility (South 1.93E-03 sec/m Wall) 3 Commodities Penetration on 1.77E-03 sec/m the RB South Wall 3

Commodities Penetration on 5.21 E-03 sec/m the RB North Wall MAC Facility Personnel 3 6.75E-03 sec/m The most limiting 0-2 hr Airlock potential release point was 3 determined to be the MAC MAC Facility Entrance 6.62E-03 sec/mi facility Personnel Airlock.

3 RB Roof Hatch 1.82E-03 sec/m 3

Stack Tunnel Door 8.55E-04 sec/m 3

East Airlock Door 1.40E-03 sec/m 3

Reactor Building Wall (Diffuse 2.1 5E-03 sec/m Area) 3 From Calculation C-1302-826-Trunion Room Door to 3.73E-03 sec/m E540-017, Revision 0 (same Turbine Bldg. as for MSIV release during a LOCA) (Ref 11 EAB Release Point Basis and Normal RB exhaust stack and All releases considered as Distance to EAB 414 m (considered as ground level releases.

applicable to all release locations)

Limiting Dispersion From calculation C-1302-826-Factors (0- 2 hr) 1.41 E-03 sec/m3 E310-018 Rev. 0 (Ref 7)

LPZ Release Point Basis and Normal RB exhaust stack and All releases considered as Distance to LPZ 3218 m (considered as ground level releases.

applicable to all release locations)

Limiting Dispersion From calculation C-1302-826-3 Factors (0- 2 hr) 1.35E-04 sec/i E310-018 Rev. 0 (Ref 7)

I CALCULATION NO. C-1 302-822-E310-082 I REV. No. 0 1 PAGENO. 13

5. REFERENCES

1. Oyster Creek Nuclear Generating Station, UFSAR, Revision 14.

2. Regulatory Guide 1.183, "Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors", July 2000.

3. NUREG/CR-6604, "RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", April1998, andl Supplements 1, June 1999, and 2, October 2002.

4. Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion",

1988.

5. Federal Guidance Report No. 12, "External Exposure to Radionuclides in Air, Water, and Soil", 1993.

6. NUREG-1465, "Accident Source Terms for Light-Water Nuclear power Plants", 1995.

7. OCNGS C-1 302-826-E310-018, "Oyster Creek Offsite Atmospheric Dispersion (x/Q)

Values for Alternative Source Term", Rev. 0.

8. G. Burley, "Evaluation of Fission Product Release and Transport", Staff Technical Paper,

,1971.

9. OCNGS C-1 302-822-E310-081, Revision 0, "Oyster Creek Onsite Atmospheric Dispersion (X/Q) for Fuel Handling Accident (FHA)", Rev. 0.

10. OCNGS C-1 302-226-E620-369, "Oyster Creek Source Term for Two Year Cycles", Rev.

0.

11. PSAT 05201 H.08, "Dose Assessment for Oyster Creek Control Room Habitability", Rev.

3.

12. OCNGS C-1 302-826-E540-017, "Calculation of OC Control Room Air Intake X/Q's for Ground Level Releases Using ARCON96", Rev. 3.

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. 14

6. CALCULATIONS This calculation evaluates the radiological dose to an operator in the Control Room and a person at the EAB and LPZ locations following a design basis FHA involving irradiated fuel that has decayed for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after occupying a critical reactor core shutdown.. This analysis uses Alternative Source Term assumptions per guidance in RG 1.183.

The RADTRAD v. 3.03computer code was used for this calculation to determine FHA doses at the three dose points cited in RG 1.183; the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and the Control Room. RADTRAD (Ref. 3) is a simplified model of RADionuclide Transport and Removal And Dose Estimation developed for the NRC and endorsed by the NRC as an acceptable methodology for reanalysis of the radiological consequences of design basis accidents.

The technical basis for the RADTRAD code is documented in Section 2 of NUREG/CR-6604. The methodologies significant to this analysis are the dose consequence analysis (NUREG Section 2.3) and the Radioactive Decay Calculations (NUREG Section 2.4).

The RADTRAD code uses a combination of tables and/or numerical models of a given source term to determine the time-dependent dose at user-specified locations for a given accident scenario.

The code also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation.

See Section 2 and subsequent sections for descriptions of the calculational simulations detailed in the tables that follow.

6.1.1. RADTRAD Run Compartment Information Hii!iil Compartment 1 2 3 Number Name Reactor Building Environment Control Room Type Other Environment Control Room Volume (ft) 1 0 27,500 Source Term Frct 1.000 0.000 0.000 Fraction Compartment Used to represent the Features ventilated radionuclide release region above the Environment No credited removal mechanisms spent fuel pool and Reactor Well during refueling.

Comments Actual volume is irrelevant, as No credited removal mechanisms the ventilated fraction is used.

RADTRAD input is set to 100 for exhaust purposes.

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGENO. 15 I 6.1.2. RADTRAD Run Transfer Pathway Information RADTRAD Tr-ansfer-lathw~a s Pathway Number 1 2 3 Name Refuel floor airspace to (High Volume-Purge+ (Control Room Exhaust)

NE virom ento Intake) Environment to Control Room to Environment Control Room Environment From - To 1-2 2-3 3-2 Transfer Mechanism Filter Filter Filter Transfer Mechanism Filter Panel - Flow rate for 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Filter Panel - Flow rate for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Filter Panel - Flow rate for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period at 14,000 cfm. ,' period at 2,000 cfm.

Details period at 1000 cfm Filter Efficiency - Efficiency is Filter Efficiency - 0.0% filter Filter Efficiency - 0.0% filter entered as 0.0% for all chemical efficiency efficiency forms of iodine, for the accident duration.

Comments Vented at an artificially high air change rate without credit for SGTS filtration.

6.1.3. RADTRAD Run Dose Location Information

___________ ~RA~DTJ 1 Dj"Dose Locations Dose Location 2 3 Number Name 'Exclusion Area Boundary Low Population Zone (LPZ) Control Room (EAB)

In Compartment Environment (2) Environment (2) Control Room (3)

Breathing Rate (m3/sec) 0-2-hour Period: 3.5E-04 hour Period:

8-24-hour 3.5E-04 Period: 1.8E-04 0-24-hour Period:

24-96-hour Period:

1.OE-0 6.0E-01 Occupancy 0-24-hour Period: 1.0 Fractions 0.6 thereafter Dispersion Ground Level Release: Ground Level Release: Ground Level Release:

Factors 2-hourPeriod: 1.10E-03 2-hour Period: 5.60E-05 2-hour Period: 6.750E-03 Comments Ground level release dispersion Ground level release dispersion Ground level release dispersion factors factors are used because the factors are used because the are used because the analyses do not analyses do not credit SGTS or analyses do not credit SGTS or credit SGTS or Secondary Containment Secondary Containment Secondary Containment Release is for two h6urs. Control Room dose calculated until effectively all activity has been exhausted 6.1.4. RADTRAD Run Source Term & Dose Conversion Factor Information RK>ADTJ4AD Source T'erm & Dose Convertsion Factoi-s Core Power 1969 MWth; 560 assemblies; 140 damaged rods with 74 rods/assembly; and radial peaking factor of 1.7 = See Section 2.1.

1969 MWth

0.003378

1.7 = 11.31 MWth.

Nuclide Inventory Attachment A ORIGEN calculated core inventory for.60 MACCS isotopes. Inventory, calculated at DBA power shown above, and See Attachments A and C.

input into the FHA NIF file with adjustments for Kr-85 and 1-131 (Attachment C).

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGENO. 16 I Release Fractions User defined Release Fractions to calculate

& Timing as effectively 100% instantaneous release, consistent with RG 1.183 guidance. Fractions shown in RFT file includes gap activity fractions combined with the applicable decontamination factors.

Dose Conversion RADTRAD Library of FGR 11 &12 values for References 4 and 5.

Factors 60 MACCS isotopes.

Decay & Enabled - Consideration of daughter products Daughter is only for conservatism Products Iodine Chemical Aerosol: 0.0000 User defined iodine chemical fractions, Fractions Elemental: 0.9700 consistent with RG 1.183 guidance.

Organic: 0.0300 Note that no filters are credited so chemical fractions are not important.

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGENO. 17

7. RESULTS AND CONCLUSIONS The RADTRAD code was used to examine the effect of the alternate source term release on offsite and CR doses. Shown below are the results, as well as the dose acceptance criteria.

Table 3: RADTRAD Analysis Results and Comparisons to the Acceptance Criteria I Dose IEAB ILPZ I CR Rem, TEDE 7.41 E-01 7.09 E-021 1.45 These results indicated that the calculated consequences of a design basis Fuel Handling Accident at or after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the fuel has occupied a critical reactor core of shutdown will be within regulatory limits.

Since the above analyses are performed without credit for secondary containment, SGTS filtration, these results indicate that immediate suspension of movement of irradiated fuel assemblies in the secondary containment would not be necessary if secondary containment isolation were lost.

NOTE: Except for the Stack Tunnel Door (assumed to be opened for maintenance during refueling) and the flanged ground level commodities penetrations on the North and South Reactor Building walls (assumed to be opened during refueling), all other potential release points are associated with personnel and equipment access doors/hatches. If any other release point is caused by the disassembly of any portion of the secondary containment boundary, specific analysis for these locations will be required to ensure atmospheric dispersion values are bounded by those used in this calculation.

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGENO. A-I I ATTACHMENT A RADTRAD Dose Conversion Factor Input File FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 Implicit daughter halflives (m) less than 90 and less thah 0.100 of parent 9 ORGANS DEFINED IN THIS FILE:

GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 60 NUCLIDIES DEFINED IN THIS FILE:

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Rb-86 Sr-89 Sr-90 Sr-91 Including: Y-91m Sr-92 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 Including:Nb-97m , Including:Nb-97 Nb-95 Mo-99 Tc-99m Ru-103 Including: Rh-103m Ru-105 Ru-106 Including:Rh-106 Rh-105 Sb-127 Sb-129 Te-127 Te-127m Te-129 Te-129m Including: Te-129 Te-131m Including: Te-131 Te-132 1-131 1-132 1-133 1-134 1-135 Including:Xe-135m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Cs-134 Cs-136 Cs-137 Including:Ba-137m Ba-137m

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. A-2 I Ba-139 D Ba-140 D La-140 W La-141 D La-142 D Ce-141 Y Ce-143 Y Ce-144 Y Including:Pr-144m, Including:Pr-144 Pr-143 Y Nd-147 Y Np-239 W Pu-238 Y Pu-239 Y CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC Kr-83m GONADS 7.310E-15 2.594E-12 3.653E-12 1.570E-16-.0O0E+00 0.000E+00 O.OOOE+00 BREAST 8.410E-15 2.527E-12 3.560E-12 l.530E-16-1.OOE+00 0.OOOE+00 O.0OOE+00 LUNGS 7.040E-15 2.379E-12 3.351E-12 1.440E-16-1.DO0E+00 O.OOOE+00 0.00E+00 RED MARR 6.430E-15 2.346E-12 3.304E-12 1.420E-16-1.OOOE+00 0.DDDE+00 O.000E+00 BONE SUR 1.880E-14 5.286E-12 7.446E-12 3.200E-16-1.OOOE+00 0.OOE+00 D.ODOE+00 THYROID 7.330E-15 2.395E-12 3.374E-12 1.450E-16-1.OOOE+00 O.00E+00 O.OOOE+00 REMAINDER 6.640E-15 2.313E-12 3.257E-12 1.400E-16-l.CD0E+00 0.OOOE+00 O.OOOE+00 EFFECTIVE 7.480E-15 2.511E-12 3.537E-12 i.520E-16-1.000E+00 D.DO0E+00 O.OOOE+00 SKIN(FGR) 2.240E-14 2.247E-11 3.164E-11 1.360E-15-I.OOOE+00 O.DOOE+00 O.OODE+00 Kr-85m GONADS 7.310E-15 2.594E-12 3.653E-12 1.570E-16-I.OOE+00 O.OOE+00 0.OOE+00 BREAST 8.410E-15 2.527E-12 3.560E-12 1.530E-16-1.O0OE+00 O.OODE+00 O.OOOE+00 LUNGS 7.040E-15 2.379E-12 3.351E-12 1.440E-16-1.OOOE+00 D.OOOE+00 O.OD0E+00 RED MARR 6.430E-15 2.346E-12 3.304E-12 1.420E-16-1.00DE+00 D.DOE+00 O.OOE+00 BONE SUR 1.880E-14 5.286E-12 7.446E-12 3.200E-16-1.0O0E+00 O.OD0E+00 O.OOOE+00 THYROID 7.330E-15 2.395E-12 3.374E-12 1.450E-16-1.OOE+00 O.OOE+00 O.OOE+00 REMAINDER 6.640E-15 2.313E-12 3.257E-12 1.400E-16-1.000E+00.0.000E+00 D.DOOE+00 EFFECTIVE 7.480E-15 2.511E-12 3.537E-12 1.520E-16-1.OO0E+00 O.0O0E+00 D.OOOE+00 SKIN(FGR) 2.240E-14 2.247E-11 3.164E-I1 1.360E-15-1.DOE+00 O.OOE+00 D.OOE+00 Kr-85 GONADS 1.170E-16 8.121E-14 1.704E-12 2.820E-18-1.0OOE+00 C.00E+00 O.ODE+00 BREAST 1.340E-16 7.891E-14 1.656E-12 2.740E-18-1.DOOE+00 O.OOOE+00 0.OOE+00 LUNGS 1.140E-16 7.056E-14 1.481E-12 2.450E-18-1.O0E+00 O.000E+00 0.ODOE+00 RED MARR 1.090E-16 6.998E-14 1.469E-12 2.430E-18-l.OC0E+00 O.DOE+00 O.OOOE+00 BONE SUR 2.200E-16 1.287E-13 2.702E-12 4.470E-18-.OOOE+00 0.000E+00 0.OOE+00 THYROID 1.180E-16 7.459E-14 1.565E-12 2.590E-18-.OOOE+00 O.0O0E+00 D.D0DE+00 REMAINDER 1.090E-16 6.941E-14 1.457E-12 2.410E-18-I. O0E+00 D.DOOE+00 O.000E+00 EFFECTIVE 1.190E-16 7.603E-14 1.596E-12 2.640E-18-1.OOE+00 O.OODE+00 O.OOOE+00 SKIN(FGR) 1.320E-14 2.304E-11 4.835E-10 8.O0E-16-1.OOOE+00 0.OO0E+00 O.00E+00 Kr-87 GONADS 4.DOOE-14 4.962E-12 5.026E-12 7.610E-16-l.OOE+00 D.DOE+00 D.ODOE+00 BREAST 4.500E-14 4.740E-12 4.802E-12 7.270E-16-1.OOE+00 D.DO0E+00 D.CO0E+00 LUNGS 4.040E-14 4.603E-12 4.663E-12 7.060E-16-l. OE+00 .OO0E+00 O.ODOE+00 RED MARR 4.OOE-14 4.708E-12 4.769E-12 7.220E-16-1.OOOE+00 D.DO0E+00 O.OOE+00 BONE SUR 6.020E-14 6.514E-12 6.598E-12 9.990E-16-1.OIE+00 O.DOOE+00 0.000E+00 THYROID 4.130E-14 4.473E-12 4.531E-12 6.860E-16-I.DO0E+00 0.DO0E+00 D.QO0E+00 REMAINDER 3.910E-14 4.590E-12 4.650E-12 7.040E-16-1.Q00E+00 0.DO0E+00 O.OOOE+00 EFFECTIVE 4.120E-14 4.773E-12 4.835E-12 7.320E-16-I.DOOE+00 0.DO0E+00 O.0OOE+00 SKIN(FGR) 1.370E-13 8.802E-11 8.916E-11 1.350E-14-.OOOE+00 O.OOE+00 0.OODE+00 Kr-88 GONADS 9.900E-14 2.278E-11 2.655E-11 1.800E-15-1.000E+00 O.00E+00 O.OO0E+00 BREAST 1.110E-13 2.177E-11 2.537E-11 1.720E-15-I.OOE+00 0.OOOE+00 O.OOE+00 LUNGS 1.010E-13 2.139E-11 2.493E-11 1.690E-15-1.OOE+00 0.OC0E+00 0.CO0E+00 RED MARR 1.OOE-13 2.190E-11 2.552E-11 1.730E-15-1.OO0E+00 O.OOOE+00 0.0OOE+00 BONE SUR 1.390E-13 2.886E-11 3.363E-11 2.280E-15-1.OCDE+00 O.OOE+00 O.OOE+00 THYROID 1.030E-13 2.012E-11 2.345E-11 1.590E-15-1.OOE+00 D.DOE+00 O.OOOE+00 REMAINDER 9.790E-14 2.139E-11 2.493E-11 1.690E-15-1.OOOE+00 D.C00E+00 O.OOE+00

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-3 EFFECTIVE 1.020E-13 2.202E-11 2.567E-11 1.740E-15-l.OOOE+00 O.DO0E+00 0.0OOE+00 SKIN(FGR) 1.350E-13 5.607E-11 6.534E-11 4.430E-15-1.0O0E+00 0.OOOE+00 O.000E+00 Kr-89 GONADS 9.900E-14 2.278E-11 2.655E-11 1.800E-15-1.OOE+00 O0OO0E+00 D.OOE+00 BREAST 1.11OE-13 2.177E-11 2.537E-11 1.720E-15-1.OOOE+00 0.OOOE+00 O.00E+00 LUNGS 1.010E-13 2.139E-11 2.493E-11 1.690E-15-1.O0OE+00 O.0OOE+00 O.OOOE+00 RED MARR 1.000E-13 2.190E-11 2.552E-11 1.730E-15-1.OO0E+00 D.DOE+00 D.DDDE+00 BONE SUR 1.390E-13 2.886E-11 3.363E-11 2.280E-15-1.000E+00 O.0ODE+00 O.OOOE+00 THYROID 1.030E-13 2.012E-11 2.345E-11 1.590E-15-1.000E+00 O.DO0E+00 0.000E+00 REMAINDER 9.790E-14 2.139E-11 2.493E-11 1.690E-15-1.O0OE+00 O.OOE+00 0.00DE+00 EFFECTIVE 1.020E-13 2.202E-11 2.567E-11 1.740E-15-1.OOOE+00 O.DO0E+00 O.OOE+00 SKIN(FGR) 1.350E-13 5.607E-11 6.534E-11 4.430E-15-1.0OOE+00 O.OO0E+00 O.OOE+00 Rb-86 GONADS 4.710E-15 2.788E-12 5.187E-11 9.740E-17-1.OD0E+00 1.340E-09 2.150E-09 BREAST 5.340E-15 2.662E-12 4.953E-11 9.300E-17-1.D0DE+00 1.330E-09 2.140E-09 LUNGS 4.710E-15 2.553E-12 4.750E-11 8.920E-17-1.0OOE+00 3.300E-09 2.140E-09 RED MARR 4.640E-15 2.619E-12 4.873E-11 9.150E-17-1.OOOE+00 2.320E-09 3.720E-09 BONE SUR 7.050E-15 3.635E-12 6.764E-11 1.270E-16-1.0ODE+00 4.270E-09 6.860E-09 THYROID 4.840E-15 2.599E-12 4.836E-11 9.080E-17-1.000E+00 1.330E-09 2.140E-09 REMAINDER 4.520E-15 2.542E-12 4.729E-11 8.880E-17-1.OOOE+00 1.380E-09 2.330E-09 EFFECTIVE 4.810E-15 2.665E-12 4.958E-11 9.310E-17-1.OOE+00 1.790E-09 2.530E-09 SKIN(FGR) 4.850E-14 2.210E-10 4.111E-09 7.720E-15-1.000E+00 O.DOE+00 D.DO0E+00 Sr-89 GONADS 7.730E-17 7.155E-14 1.436E-12 2.490E-18-1.OOE+00 7.950E-12 8.050E-12 BREAST 9.080E-17 7.212E-14 1.447E-12 2.510E-18-1.DCDE+00 7.960E-12 7.980E-12 LUNGS 7.080E-17 5.689E-14 1.142E-12 1.980E-18-1.00DE+00 8.350E-08 7.970E-12 RED MARR 6.390E-17 5.345E-14 1.073E-12 1.860E-18-1.OOOE+00 1.070E-10 1.080E-10 BONE SUR 1.940E-16 1.560E-13 3.131E-12 5.430E-18-1.OOOE+00 1.590E-D0 1.610E-10 THYROID 7.600E-17 6.063E-14 1.217E-12 2.110E-18-1.DODE+00 7.960E-12 7.970E-12 REMAINDER 6.710E-17 5.603E-14 1.124E-12 1.950E-18-1.OO0E+00 3.970E-09 8.250E-09 EFFECTIVE 7.730E-17 6.523E-14 1.309E-12 2.270E-18-1.0OOE+00 1.120E-08 2.500E-09 SKIN(FGR) 3.690E-14 1.914E-10 3.841E-09 6.660E-15-l.OOE+00 O.OOOE+00 0.000E+00 Sr-90 GONADS 7.780E-18 9.590E-15 2.014E-13 3.330E-19-1.OOOE+00 2.690E-10 5.040E-11 BREAST 9.490E-18 1.008E-14 2.116E-13 3.500E-19-1.OOOE+00 2.690E-10 5.040E-11 LUNGS 6.440E-18 6.307E-15 1.324E-13 2.190E-19-1.0O0E+00 2.860E-06 5.040E-11 RED MARR 5.440E-18 5.558E-15 1.167E-13 1.930E-19-1.OODE+00 3.280E-08 6.450E-09 BONE SUR 2.280E-17 2.393E-14 5.025E-13 8.310E-19-1.OODE+00 7.090E-08 1.390E-08 THYROID 7.330E-18 7.171E-15 1.506E-13 2.490E-19-1.OD0E+00 2.690E-10 5.040E-11 REMAINDER 6.110E-18 6.422E-15 1.348E-13 2.230E-19-1.OOOE+00 5.730E-09 6.700E-09 EFFECTIVE 7.530E-18 8.179E-15 1.717E-13 2.840E-19-1.OO0E+00 3.510E-07 3.230E-09 SKIN(FGR) 9.200E-15 4.032E-12 8.465E-11 1.400E-16-1.0OOE+o0 O.DOOE+00 0.000E+00 Sr-91 GONADS 4.819E-14 2.155E-11 5.062E-11 1.026E-15-1.0O0E+00 5.669E-11 2.520E-10 BREAST 5.477E-14 2.059E-11 4.838E-11 9.806E-16-I.OO0E+00 1.775E-11 3.676E-11 LUNGS 4.803E-14 1.970E-11 4.626E-11 9.376E-16-l.C0DE+00 2.170E-09 1.055E-11 RED MARR 4.691E-14 2.011E-11 4.722E-11 9.570E-16-.O0DE+00 2.275E-11 5.659E-11 BONE SUR 7.674E-14 2.852E-11 6.709E-11 1.360E-15-.OOOE+00 1.306E-11 2.070E-11 THYROID 4.938E-14 2.035E-Il 4.782E-11 9.693E-16-.OODE+00 9.930E-12 1.968E-12 REMAINDER 4.610E-14 1.948E-11 4.573E-11 9.268E-16-.OOOE+00 5.802E-10 2.557E-09 EFFECTIVE 4.924E-14 2.057E-11 4.832E-11 9.793E-16-.OOE+00 4.547E-10 8.455E-10 SKIN(FGR) 9.938E-14 1.748E-10 3.987E-10 8.080E-15-I.OOOE+00 O.0D0E+00 O.000E+00 Sr-92 GONADS. 6.610E-14 1.593E-11 1.830E-11 1.300E-15-I.CO0E+00 1.020E-11 8.180E-11 BREAST 7.480E-14 1.520E-11 1.745E-11 1.240E-15-I.DO0E+00 6.490E-12 1.700E-11 LUNGS 6.670E-14 1.483E-11 1.703E-11 1.210E-15-I.000E+00 1.050E-09 7.220E-12 RED MARR 6.620E-14 1.520E-11 1.745E-11 1.240E-15-I.DODE+00 6.980E-12 2.290E-11 BONE SUR 9.490E-14 2.010E-11 2.308E-11 1.640E-15-.O00E+00 4.360E-12 8.490E-12 THYROID 6.820E-14 1.446E-11 1.661E-11 1.180E-15-.0OO0E+00 3.920E-12 1.300E-12 REMAINDER 6.450E-14 1.471E-11 1.689E-11 1.200E-15-.ODOE+00 2.900E-10 1.720E-09 EFFECTIVE 6.790E-14 1.532E-11 1.759E-11 1.250E-15-I.DO0E+00 2.180E-10 5.430E-10 SKIN(FGR) 8.560E-14 2.280E-11 2.618E-11 1.860E-15-I.ODDE+00 O.OOOE+00 O.ODDE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. A-4 I Y-90 GONADS 1.890E-16 1. 586E-13 1. 601E-12 5.750E-18-1 .OOOE+00 5. 170E-13 1.430E-14 BREAST 2.200E-16 1. 578E-13 1 593E-12 5.720E-18-1.OO0E+00 5. 170E-13 1.270E-14 LUNGS 1.770E-16 1 . 313E-13 1 326E-12 4.760E-18-1 .OOE+00 9. 310E-09 1.260E-14 RED MARR 1. 620E-16 1 .261E-13 1 273E-12 4.570E-18-1 .OOE+00 1. 520E-11 3.700E-13 BONE SUR 4. 440E-16 3. 228E-13 3 259E-12 1.170E-17-1. 00E+00 1. 510E-I1 3. 670E-13 THYROID 1. 870E-16 1. 385E-13 1. 398E-12 5.020E-18-1 .OOE+00 5.170E-13 1 .260E-14 REMAINDER 1. 680E-16 1 .291E-13 1. 303E-12 4.68OE718-1 .OOOE+00 3. 870E-09 9. 680E-09 EFFECTIVE 1. 900E-16 1. 468E-13 1. 482E-12 5.320E-18-1 .0OE+00 2 .280E-09 2. 910E-09 SKIN.(FGR) 6. 240E-14 2 897E-10 2. 924E-09 1.050E-14-1 .OOOE+00 0. OOE+00 0. OOOE+00 Y-91 GONADS 2. 560E-16 1 .756E-13 3. 546E-12 6.1OE-18-1.OO0E+00 8.200E-12 3.540E-12 BREAST 2 .930E-16 1 713E-13 3. 459E-12 5.960E-18-1.OOE+00 8.920E-12 5.540E-13 LUNGS 2. 500E-16 1 .526E-13 3. 082E-12 5. 310E-18-1 .OOOE+00 9. 870E-08 2.020E-13 RED MARR 2.410E-16 1. 521E-13 3. 070E-12 5 .290E-18-1 .OOE+00 3. 190E-10 6. 590E-12 BONE SUR 4. 560E-16 2. 903E-13 5. 862E-12 1. 010E-17-1 .000E+00 3. 180E-10 6. 130E-12 THYROID 2. 600E-16 1. 564E-13 3 157E-12 5. 440E-18-1. OOOE+00 8. 500E-12 1.290E-13 REMAINDER 2. 390E-16 1. 509E-13 3. 047E-12 5 .250E-18-1. OOOE+00 4. 200E-09 8.570E-09 EFFECTIVE 2. 600E-16 1. 650E-13 3. 332E-12 5. 740E-18-1. 00E+00 1. 320E-08 2. 570E-09 SKIN(FGR) 3.850E-14 1. 989E-10 4. 016E-09 6. 920E-15-1. OOOE+00 0. OOE+00 0. 000E+00 Y-92 GONADS 1. 270E-14 3. 855E-12 4 .872E-12 2.650E-16-1.OO0E+00 2. 610E-12 1. 960E-11 BREAST 1. 440E-14 3. 680E-12 4 .652E-12 2. 530E-16-1.0O0E+00 1.500E-12 3. 550E-12 LUNGS 1. 270E-14 3. 535E-12 4. 468E-12 2 430E-16-1.0O0E+00 1. 240E-09 1.390E-12 RED MARR 1. 250E-14 3 608E-12 4. 560E-12 2. 480E-16-1.O00E+00 2. 070E-12 4. 910E-12 BONE SUR 1. 950E-14 5. 091E-12 6. 435E-12 3. 500E-16-1.OOOE+00 1. 510E-12 1.750E-12

.THYROID 1. 300E-14 3. 579E-12 4 .523E-12 2. 460E-16-1.0OOE+00 1. 050E-12 1.770E-13 REMAINDER 1. 220E-14 3. 506E-12 4 431E-12 2. 410E-16-1.OO0E+00 2. 030E-10 1.700E-09

.EFFECTIVE 1. 300E-14 3 680E-12 4. 652E-12 2. 530E-16-1.OO0E+00 2. ll0E-10 5. 150E-10 SKIN (FGR) 1 .140E-13 2 .022E-10 2 .556E-10 1. 390E-14-1.OO0E+00 0. 000E+00 o.000E+00 Y-93 GONADS 4. 670E-15 2 .108E-12 4. 989E-12 9. 510E-17-1.OO0E+00 5. 310E-12 2 .200E-II BREAST 5. 300E-15 2 .026E-12 4. 794E-12 9. 140E-17-1 .OOOE+00 1.740E-12 3. 130E-12 LUNGS 4. 680E-15 1. 937E-12 4 . 585E-12 8 .740E-17-1. OOOE+00 2. 520E-09 8.670E-13 RED MARR 4. 580E-15 1 . 972E-12 4. 669E-12 8. 900E-17-1. OOE+00 4. 040E-12 4. 930E-12 BONE SUR 7. 580E-15 2. 948E-12 6 977E-12 1. 330E-16-1. 00E+00 3.140E-12 1.730E-12 THYROID 4 .790E-15 1 . 908E-12 4. 516E-12 8. 610E-17-1. OOOE+00 9. 260E-13 1.260E-13 REMAINDER 4 510E-15 1. 919E-12 4. 543E-12 8. 660E-17-1. OOE+00 9. 250E-10 4.090E-09 EFFECTIVE 4. 800E-15 2. 021E-12 4. 784E-12 9. 120E-17-1 .00E+00 5.820E-10 1.230E-09 SKIN (FGR) 8. 500E-14 2 .726E-10 6. 452E-10 1. 230E-14-1 .OOE+00 0 . OOE+00, o.000E+00 Zr-95 GONADS 3. 530E-14 2. 182E-11 4 421E-10 7. 590E-16-1 .OOOE+00 1. 880E-09 8. 160E-10 BREAST 4. OlOE-14 2 084E-11 4 223E-10 7. 250E-16-1 .0OE+00 1. 910E-09 1. 050E-10 LUNGS 3. 510E-14 1. 989E-11 4. 030E-10 6. 920E-16-1 .OOOE+00 2. 170E-09 2. 340E-11 RED MARR 3. 430E-14 2 .030E-11 4. 112E-10 7. 060E-16-1 .OOE+00 1. 300E-08 2. 140E-10 BONE SUR 5. 620E-14 2 875E-11 5. 824E-10 1 .0OE-15-1 .OOOE+00 1 . 030E-07 4. 860E-10 THYROID 3. 610E-14 2 .076E-11 4 .205E-10 7. 220E l.OOE+00 i. 440E-09 8 .270E-12 REMAINDER 3. 360E-14 1. 963E-11 3.978E-10 6. 830E-16-1 .OOOE+00 2. 280E-09 2 .530E-09 EFFECTIVE 3. 600E-14 2. 078E-11 4.211E-10 7 .230E-16-1.OOOE+00 6. 390E-09 1 .020E-09 SKIN(FGR) 4 500E-14 2. 561E-I1 5. 190E-10 8. 910E-16-1. OOOE+00 0. 000E+00 0 . 000E+00 Zr-97 GONADS 4. 331E-14 2 179E-11 7 .799E-11 9 .253E-16-1. OOOE+00 1. 840E-10 6. 228E-10 BREAST 4. 928E-14 2. 083E-11 7. 455E-11 8. 846E-16-1 .O0E+00 4. 706E-11 8. 137E-11 LUNGS 4. 322E-14 1. 992E-11 7. 127E-11 8. 456E-16-1 .OOE+00 4 108E-09 1. 770E-11 RED MARR 4 .224E-14 2 034E-11 7. 279E-11 8. 634E-16-1 .OOE+00 6. 376E-11 1. 302E-10 BONE SUR 6. 897E-14 2 .881E-11 1. 031E-10 1. 224E-15-1 .OOOE+00 3. 504E-11 4. 558E-11 THYROID 4. 443E-14 2 061E-11 7. 377E-II 8. 755E-16-1 .OOE+00 2. 315E-11 2. 671E-12 REMAINDER 4 139E-14 1 . 966E-11 7 035E-11 8. 345E-16-1 .OOOE+00 2. 041E-09 6. 990E-09 EFFECTIVE 4 432E-14 2. 078E-11 7. 438E-11 8. 824E-16-1. 00E+00 1. 171E-09 2 .283E-09 SKIN(FGR) 9. 835E-14 2 .281E-10 8. 148E-1O 9. 587E-15-1. 000E+00 0. 000E+00 0. 000E+00 Nb-95 GONADS 3.660E-14 2.253E-11 4.435E-10 7.850E-16-1.000E+00 4.320E-10 8.050E-10 BREAST 4.160E-14 2.150E-11 4.231E-10 7.490E-16-1.000E+00 4.070E-10 1.070E-10

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 1 PAGENO. A-5 LUNGS 3. 650E-14 2.055E-II 4. 045E-10 7.160E-16-1.000E+00 8. 320E-09 2 .740E-I1 RED MARR 3.560E-14 2. 101E-11 4.135E-10 7.320E-16-1.000E+00 4. 420E-10 1. 990E-10 BONE SUR 5.790E-14 2.957E-11 5.819E-10 1.030E-15-1.000E+00 5. 130E-10 2. 940E-10 THYROID 3.750E-14 2.144E-11 4.220E-10 7.470E-16-1.000E+00 3. 580E-10 1.180E-11 REMAINDER 3.490E-14 2.032E-11 4. 0OOE-10 7.080E-16-1.000E+00 1.070E-09 1.470E-09 EFFECTIVE 3. 740E-14 2. 147E-11 4.226E-10 7.480E-16-1.000E+00 1. 570E-09 6. 950E-10 SKIN(FGR) 4.300E-14 2. 598E-11 5.112E-10 9.050E-16-1.000E+00 0. OOOE+00 0. OOOE+00 Mo-99 GONADS 7.130E-15 4.282E-12 4.403E-11 1.550E-16-1.000E+00 9.510E-il 2.180E-10 BREAST 8.130E-15 4.116E-12 4.233E-11 1.490E-16-1.OOOE+00 2.750E-11 3.430E-I1 LUNGS 7.060E-15 3. 867E-12 3. 977E-I1 1.400E-16-1. 00E+00 4.290E-09 1.510E-Il RED MARR 6. 820E-15 3. 923E-12 4.034E-11 1.420E-16-1.O0OE+00 5.240E-11 8.320E-Il BONE SUR 1.240E-14 6. 105E-12 6. 278E-11 2.210E-16-1.000E+00 4.130E-11 6.320E-Il THYROID 7.270E-15 4 .033E-12 4.147E-11 1.460E-16-1.000E+00 1.520E-11 1.030E-11 REMAINDER 6. 740E-15 3.812E-12 3.920E-11 1.380E-16-1.OOOE+00 1.740E-09 4.280E-09 EFFECTIVE 7.280E-15 4 .061E-12 4.176E-11 1.470E-16-1.000E+00 1.070E-09 1.360E-09 SKIN(FGR) 3. 140E-14 1.039E-10 1.068E-09 3.760E-15-1.000E+00 0.OOOE+00 0.OOOE+00 Tc-99m GONADS 5.750E-15 2.334E-12 3. 877E-12 1.240E-16-1.000E+00 2. 770E-12 9. 750E-12 BREAST 6. 650E-15 2.258E-12 3. 752E-12 1.200E-16-1.OOOE+00 2.150E-12 3. 570E-12 LUNGS 5.490E-15 2.127E-12 3. 533E-12 1.130E-16-1.000E+00 2.280E-11 3. 140E-12 RED MARR 4. 910E-15 2.070E-12 3. 439E-12 1.100E-16-1.OOOE+00 3. 360E-12 6.290E-12 BONE SUR 1. 630E-14 5. 383E-12 8 . 942E-12 2.860E-16-1.OO0E+00 2.620E-12 4 .060E-12 THYROID 5. 750E-15 2.145E-12 3.564E-12 1.140E-16-1.000E+00 5. OlE-1I 8.460E-li REMAINDER 5.150E-15 2.070E-12 3. 439E-12 1.100E-16-1.000E+00 1. 020E-I1 3. 340E-11 EFFECTIVE 5.890E-15 2.277E-12 3. 783E-12 1.210E-16-1.OOOE+00 8.800E-12 1. 680E-Il SKIN (FGR) 7.140E-15 2 .710E-12 4.502E-12 1.440E-16-1.000E+00 0. OOOE+00 0. 000E+00 Ru-103 GONADS 2. 191E-14 1. 404E-11 2. 783E-10 4. 892E-16-1.000E+00 3. 070E-10 5.720E-10 BREAST 2.512E-14 1. 350E-11 2. 677E-10 4. 705E-16-1.000E+00 3. 11OE-10 1. 200E-10 LUNGS 2. 180E-14 1. 273E-11 2. 522E-10 4. 432E-16-1.OOOE+00 1. 561E-08 7. 310E-II RED MARR 2. 100E-14 1. 287E-11 2. 551E-10 4. 483E-16-1.000E+00 3. 190E-10 1. 660E-10 BONE SUR 3.892E-14 1. 958E-11 3. 882E-10 6. 823E-16-1.0OOE+00 2. 370E-10 9. 631E-li THYROID 2.241E-14 1. 331E-11 2 639E-10 4. 638E-16-1.OOOE+00 2. 570E-10 6. 250E-II REMAINDER 2.080E-14 1 .248E-11 2. 472E-10 4. 346E-16-1.OOOE+00 1.250E-09 2. 110E-09 EFFECTIVE 2.251E-14 1. 332E-11 2 641E-10 4. 642E-16-1.OOOE+00 2 .. 421E-09 8.271E-10 SKIN(FGR) 2. 774E-14 1. 785E-11 3. 543E-10 6 .229E-16-1.OOOE+00 0. 000E+00 0. OOOE+00 Ru-105 GONADS 3. 720E-14 1. 327E-11 1. 861E-11 8. 070E-16-1. OOOE+00 1. 590E-il 9. 670E-lI BREAST 4. 240E-14 1. 271E-11 1. 783E-11 7. 730E-16-1.00O0E+00 6. 610E-12 1. 590E-11 LUNGS 3. 700E-14 1. 210E-11 1. 697E-11 7. 360E-16-1 .OOOE+00 5. 730E-10 6 .210E-12 RED MARR 3. 590E-14 1. 230E-11 1. 725E-11 7. 480E-16-1 .OOOE+00 7.700E-12 2. 350E-11 BONE SUR 6 .280E-14 1. 809E-11 2. 537E-11 1. 100E-15-1 .OOOE+00 4.620E-12 8 .890E-12 THYROID 3. 800E-14 1. 260E-11 1. 766E-11 7. 660E-16-1 .OOOE+00 4.150E-12 1. 820E-12 REMAINDER 3. 540E-14 1 189E-11 1. 667E-11 7. 230E .OOOE+00 1. 610E-10 8. 540E-I0 EFFECTIVE 3. 810E-14 1 .265E-11 1. 773E-11 7. 690E .OOOE+00 1.230E-10 2. 870E-I0 SKIN(FGR) 6. 730E-14 7. 368E-I1 1. 033E-10 4. 480E-15-1. OOOE+00 0. 000E+00 0. OOOE+00 Ru-106 GONADS 1. OlE-14 6. 411E-12 1. 340E-10 2.230E-16-1.OOOE+00 1. 300E-09 1. 640E-09 BREAST 1. 160E-14 6 152E-12 1 .286E-10 2.140E-16-1.OOOE+00 1. 780E-09 1. 440E-&9 LUNGS 1. 01OE-14 5 836E-12 1. 220E-10 2.030E-16-1.OOOE+00 1. 040E-06 1 .420E-09 RED MARR 9..750E-15 5 893E-12 1. 232E-10 2.050E-16-1.OOOE+00 1. 760E-09 1. 460E-09 BONE SUR 1.720E-14 8 883E-12 1. 856E-10 3.090E-16-1.OOOE+00 1. 610E-09 1. 430E-09 THYROID l.030E-14 .6.066E-12 1. 268E-10 2.110E-16-1.OOOE+00 1. 720E-09 1. 410E-09 REMAINDER 9.630E-15 5.721E-12 1. 196E-10 1.990E-16-1.OOOE+00 1. 200E-08 2. 11OE-08 EFFECTIVE 1.040E-14 6.095E-12 1. 274E-10 2.120E-16-1.OOOE+00 1 .290E-07 7 400E-09 SKIN(FGR) 1.090E-13 4.082E-I0 8.531E-09 1.420E-14-1.OOOE+00 0. 000E+00 0 000E+00 Rh-105 GONADS 3.640E-15 2. 127E-12 1.411E-11 7.980E-17-1.OOOE+00 2. lOE-lI 5. 800E-I1 BREAST 4.160E-15 2 .'063E-12 1.369E-11 7.740E-17-1.OOOE+00 5. 610E-12 8.970E-12 LUNGS 3.570E-15 1. 935E-12 1.284E-11 7.260E-17-1.OOOE+00 9. 580E-10 3.860E-12 RED MARR 3. 380E-15 1. 946E-12 1.291E-11 7.300E-17-1.OOOE+00 7. 770E-12 1.470E-1I BONE SUR 7.530E-15 3.332E-12 2.210E-11 1.250E-16-1.OOOE+00 4. 460E-12 6. 750E-12

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-6 THYROID 3.680E-15 1.983E-12 1.316E-11 7.440E-17-1.OOOE+00 2.880E-12 2.910E-12 REMAINDER 3.390E-15 1.885E-12 1.250E-11 7.070E-17-1.O0OE+00 4.530E-10 1.270E-09 EFFECTIVE 3.720E-15 2.031E-12 1.347E-11 7.620E-17-1.O00E+00 2.580E-10 3.990E-10 SKIN(FGR) 1.070E-14 4.691E-12 3.112E-11 1.760E-16-1.0OOE+00 0.OD0E+00 0.OOE+00 Sb-127 GONADS 3.260E-14 1.985E-11 2.441E-10 7.100E-16-1.OOOE+00 2.520E-10 6.140E-10 BREAST 3.720E-14 1.904E-11 2.341E-10 6.810E-16-1.OOE+00 9.120E-11 7.600E-11 LUNGS 3.240E-14 1.809E-11 2.224E-10 6.470E-16-1.000E+00 6.940E-09 1.570E-11 RED MARR 3.140E-14 1.834E-11 2.255E-10 6.560E-16-1.OOE+00 1.610E-10 1.330E-10 BONE SUR 5.520E-14 2.720E-11 3.345E-10 9.730E-16-1.D0DE+00 1.340E-10 5.240E-11 THYROID 3.330E-14 1.884E-11 2.317E-10 6.740E-16-1.DODE+00 6.150E-11 4.640E-12 REMAINDER 3.090E-14 1.775E-11 2.183E-10 6.350E-16-1.DODE+00 2.330E-09 5.870E-09 EFFECTIVE 3.330E-14 1.890E-11 2.324E-10 6.760E-16-1.0DDE+00 1.630E-09 1.950E-09 SKIN(FGR) 5.580E-14 7.967E-11 9.799E-10 2.850E-15-1.ODDE+00 O.D0DE+00 O.OOOE+00 Sb-129 GONADS 6.970E-14 2.336E-11 3.231E-11 1.440E-15-1.DOE+00 2A150E-11 1.510E-10 BREAST 7.910E-14 2.222E-11 3.074E-11 1.370E-15-1.O0OE+00 1.280E-11 2.560E-11 LUNGS 6.980E-14 2.141E-11 2.962E-11 1.320E-15-1.000E+00 8.980E-10 9.390E-12 RED MARR 6.860E-14 2.190E-11 3.029E-11 1.350E-15-1.000E+00 1.700E-11 3.670E-11 BONE SUR 1.070E-13 3.033E-11 4.196E-11 1.870E-15-1.OOOE+00 1.460E-11 1.340E-11 THYROID 7..160E-14 2.174E-11 3.007E-11 1.340E-15-1.OOOE+00 9.720E-12 1.470E-12 REMAINDER 6.710E-14 2.125E-11 2.939E-11 1.310E-15-1.O0OE+00 1.870E-10 1.450E-09 EFFECTIVE 7.140E-14 2.238E-ii 3.096E-11 i.380E-15-1.0O0E+00 1.740E-10 4.840E-10 SKIN(FGR) 1.050E-13 8.273E-11 1.144E-10 5.100E-15-1.DO0E+00 O.0OOE+00 0.OD0E+00 Te-127 GONADS 2.370E-16 1.191E-13 2.661E-13 5.480E-18-1.OO0E+00 2.020E-12 4.020E-12 BREAST 2.730E-16 1.158E-13 2.588E-13 5.330E-18-1.D00E+00 1.880E-12 3.OOOE-12 LUNGS 2.320E-16 1.060E-13 2.370E-13 4.880E-18-1.OD0E+00 4.270E-10 2.890E-12 RED MARR 2.210E-16 1.058E-13 2'.365E-13 4.870E-18-1.0ODE+00 4.090E-12 6.570E-12 BONE SUR 4.650E-16 1.862E-13 4.162E-13 8.570E-18-1.000E+00 4.090E-12 6.460E-12 THYROID 2.400E-16 1.106E-13 2.472E-13 5.090E-18-1.000E+00 1.840E-12 2.860E-12 REMAINDER 2.210E-16 1.036E-13 2.316E-13 4.770E-18-1.O00E+00 1.110E-10 6.130E-10 EFFECTIVE 2.420E-16 1.125E-13 2.515E-13 5.180E-18-1.0O0E+00 8.600E-11 1.870E-10 SKIN(FGR) 1.140E'-14 1.173E-11 2.622E-11 5.400E-16-1.000E+00 0.D00E+00 0.000E+00 Te-127m GONADS 1.900E-16 4.689E-13 9.642E-12 1.630E-17-1.000E+00 1.100E-10 1.250E-10 BREAST 2.690E-16 5.150E-13 1.059E-11 1.790E-17-1.OOOE+00 1.100E-10 9.740E-11 LUNGS 7.620E-17 1.602E-13 3.295E-12 5.570E-18-1.000E+00 3.340E-08 9.620E-11 RED MARR 6.430E-17 1.249E-13 2.567E-12 4.340E-18-1.000E+00 5.360E-09 5.430E-09 BONE SUR 3.940E-16 9.005E-13 1.852E-11 3.130E-17-1.D0OE+00 2.040E-08 2.070E-08 THYROID 1.500E-16 2.779E-13 5.714E-12 9.660E-18-1.DODE+00 9.660E-11 9.430E-11 REMAINDER 8.640E-17 1.999E-13 4.111E-12 6.950E-18-1.OO0E+00 1.660E-09 2.980E-09 EFFECTIVE 1.470E-16 3.251E-13 6.684E-12 1.130E-17-1.OO0E+00 5.810E-09 2.230E-09 SKIN(FGR) 8.490E-16 1.496E-12 3.076E-11 5.200E-17-1.OD0E+00 0.OO0E+00 0.OOOE+00 Te-129 GONADS 2.710E-15 3.889E-13 3.922E-13 6.510E-17-1.OD0E+00 5.050E-13 1.590E-12 BREAST 3.120E-15 3.800E-13 3.832E-13 6.360E-17-1.ODOE+00 5.390E-13 6.050E-13 LUNGS 2.640E-15 3.298E-13 3.326E-13 5.520E-17-1.000E+00 1.530E-10 4.910E-13 RED MARR 2.540E-15 3.298E-13 3.326E-13 5.520E-17-1.OOOE+00 6.190E-13 7.640E-13 BONE SUR 4.880E-15 5.753E-13 5.802E-13 9.630E-17-1.OOOE+00 6.220E-13 5.400E-13 THYROID 2.740E-15 3.525E-13 3.555E-13 5.900E-17-1.OOOE+00 5.090E-13 3.360E-13 REMAINDER 2.520E-15 3.262E-13 3.289E-13 5.460E-17-1.OOOE+00 7.280E-12 1.790E-10 EFFECTIVE 2.750E-15 3.590E-13 3.621E-13 6.010E-17-1.OOOE+00 2.090E-11 5.450E-11 SKIN(FGR) 3.570E-14 3.429E-11 3.458E-11 5.740E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 Te-129m GONADS 3.321E-15 2.206E-12 4.799E-11 8.561E-17-1.OOOE+00 1.783E-10 2.420E-10 BREAST 3.838E-15 2.181E-12 4.739E-11 8.454E-17-i.OOOEt00 1.694E-10 1.664E-l0 LUNGS 3.176E-15 1.741E-12 3.815E-11 6.808E-17-1.OOOE+00 4.040E-08 1.593E-10 RED MARR 3.071E-15 1.729E-12 3.793E-11 6.768E-17-1.OOOE+00 3.100E-09 3.500E-09 BONE SUR 5.772E-15 3.287E-12 7.147E-11 1.275E-16-1.OOOE+00 7.050E-09 7.990E-09 THYROID 3.341E-15 1.923E-12 4.201E-11 7.495E-17-1.OOOE+00 1.563E-10 1.572E-10 REMAINDER 3.048E-15 1.746E-12 3.822E-11 6.819E-17-1.OOOE+00 3.275E-09 7.196E-09 EFFECTIVE 3.337E-15 1.974E-12 4.308E-11 7.686E-17-1.OOOE+00D6.484E-09 2.925E-09

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-7 SKIN(FGR) 3.811E-14 1.501E-10 3.360E-09 6.001E-15-1.000E+00.0.000E+00 O.0O0E+00 Te-13lm GONADS 7.292E-14 4.020E-11 2.343E-10 1.535E-15-1.0OOE+00 2.345E-10 7.415E-10 BREAST 8.286E-14 3.853E-11 2.246E-10 1.472E-15-1.OOOE+00 9.309E-11 1.361E-10 LUNGS 7.265E-14 3.657E-l1 2.131E-10 1.397E-15-1.OOOE+00 2.296E-09 6.335E-11 RED MARR 7.097E-14,3.736E-lI 2.178E-I0 1.427E-15-1.0O0E+00 1.417E-10 2.435E-10 BONE SUR 1.174E-13 5.467E-11 3.189E-10 2.090E-15-1.OOOE+00 2.276E-10 3.248E-10 THYROID 7.471E-14 3.741E-11 2.181E-10 1.429E-15-1.OO0E+00 3.669E-08 4.383E-08 REMAINDER 6.965E-14 3.626E-11 2.113E-10 1.385E-15-1.OO0E+00 9.509E-10 3.153E-09 EFFECTIVE 7 . 4 6 3 E-1 4 3.825E-11 2.229E-10 1.461E-15-1.DODE+00 1.758E-09 2.514E-09 SKIN(FGR) 1.038E-13 1.033E-10 6.188E-10 4.056E-15-1.OO0E+00 C.000E+00 O.OOOE+00 Te-132 GONADS 1.020E-14 6.812E-12 7.706E-11 2.450E-16-1.OOOE+00 4.150E-10 5.410E-10 BREAST 1.180E-14 6.756E-12 7.643E-11 2.430E-16-1.0OOE+00 3.630E-10 3.500E-10 LUNGS 9.650E-15 5.727E-12 6.479E-11 2.060E-16-1.OOOE+00 1I.670E-09 3.300E-10 RED MARR 8.950E-15 5.588E-12 6.322E-11 2.010E-16-1.OD0E+00 4.270E-10 4.440E-10 BONE SUR 2.420E-14 1.273E-11 1.441E-10 4.580E-16-1.0O0E+00 7.120E-10 8.300E-10 THYROID 1.020E-14 5.978E-12 6.762E-11 2.150E-16-1.OOE+00 6.280E-08 5.950E-08 REMAINDER 9.160E-15 5.644E-12 6.385E-11 2.030E-16-1.0OOE+00 7.890E-10 1.490E-09 EFFECTIVE 1.030E-14 6.339E-12 7.171E-11 2.280E-16-1.OOOE+00 2.550E-09 2.540E-09 SKIN(FGR) 1.390E-14 8.313E-12 9.405E-11 2.990E-16-1.OOOE+00 O.OOOE+00 O.OO0E+00 1-131 GONADS 1.780E-14 l.119E-11 1.789E-10 3.940E-16-1.DODE+00 2.530E-11 4.070E-11 BREAST 2.040E-14 1.082E-11 1.730E-10 3.810E-16-1.OOOE+00 7.880E-11 1.210E-10 LUNGS 1.760E-14 1.016E-11 1.626E-10 3.580E-16-1.OO0E+00 6.570E-10 1.020E-10 RED MARR 1.680E-14 1.022E-11 1.635E-10 3.600E-16-1.OOE+00 6.260E-11 9.440E-11 BONE SUR 3.450E-14 1.675E-11 2.679E-10 5.900E-16-1.OOOE+00 5.730E-11 8.720E-11 THYROID 1.810E-14 1.053E-11 1.685E-10 3.710E-16-1.OOOE+00 2.920E-07 4.760E-07 REMAINDER 1.670E-14 9.908E-12 1.585E-10 3.490E-16-1.0OOE+00 8.030E-11 1.570E-10 EFFECTIVE 1.820E-14 1.067E-11 1.707E-10 3.760E-16-1.DOE+00 8.890E-09 1.440E-08 SKIN(FGR) 2.980E-14 1.825E-11 2.920E-10 6.430E-16-1.OOE+00 O.OOOE+00 O.OOE+00 1-132 GONADS 1.090E-13 2.523E-11 2.771E-11 2.320E-15-1.ODOE+00 9.950E-12 2.330E-11 BREAST 1.240E-13 2.414E-11 2.652E-11 2.220E-15-1.OOOE+00 1.410E-11 2.520E-11 LUNGS 1.090E-13 2.305E-11 2.532E-11 2.120E-15-1.OOOE+00 2.710E-10 2.640E-11 RED MARR 1.070E-13 2.360E-11 2.592E-11 2.170E-15-1.OOOE+00 1.400E-11 2.460E-11 BONE SUR 1.730E-13 3.327E-11 3.655E-11 3.060E-15-1.000E+00 1.240E-11 2.190E-11 THYROID 1.120E-13 2.381E-11 2.616E-11 2.190E-15-1.OODE+00 1.740E-09 3.870E-09 REMAINDER .1.050E-13 2.283E-11 2.509E-11 2.100E-15-1.DODE+00 3.780E-11 1.650E-10 EFFECTIVE 1.120E-13 2.403E-11 2.640E-11 2.210E-15-1.OOOE+00 1.030E-10 1.820E-10 SKIN(FGR) 1.580E-13 8.199E-11 9.007E-11 7.540E-15-1.000E+00 O.OOOE+00 O.OOOE+00 1-133 GONADS 2.870E-14 1.585E-11 6.748E-11 6.270E-16-I.OOOE+00 1.950E-11 3.630E-11 BREAST 3.280E-14 1.519E-11 6.468E-11 6.010E-16-1.ODOE+00 2.940E-11 4.680E-11 LUNGS 2.860E-14 1.446E-11 6.156E-11 5.720E-16-I .OOE+00 8.200E-10 4.530E-11 RED MARR 2.770E-14 1.466E-11 6.242E-11 5.800E-16-I.OOOE+00 2.720E-11 4.300E-11 BONE SUR 4.870E-14 2.161E-11 9.202E-11 8.550E-16-I.OD0E+00 2.520E-11 4.070E-11 THYROID 2.930E-14 1.502E-11 6.393E-11 5.940E-16-I.CO0E+00 4.860E-08 9.100E-08 REMAINDER 2.730E-14 1.418E-11 6.038E-11 5.610E-16-I.OOOE+00 5.OOOE-f1 1.550E-10 EFFECTIVE 2.940E-14 1.509E-11 6.425E-11 5.970E-16-.O00E+00 1.580E-09 2.800E-09 SKIN(FGR) 5.830E-14 1.150E-10 4.897E-10 4.550E-15-I.OO0E+00 O.OOOE+00 O.OOOE+00 1-134 GONADS 1.270E-13 1.200E-11 1.202E-11 2.640E-15-I.OOOE+00 4.250E-12 1.100E-11 BREAST 1.440E-13 1.145E-11 1.147E-11 2.520E-15-1.OIE+00 6.170E-12 1.170E-11 LUNGS 1.270E-13 1.100E-11 1.102E-11 2.420E-15-I.ODOE+00 1.430E-10 1.260E-11 RED MARR 1.250E-13 1.127E-11 1.129E-11 2.480E-15-I.OOOE+00 6.080E-12 1.090E-11 BONE SUR 1.960E-13 1.568E-11 1.571E-11 3.450E-15-I.0OOE+00 5.310E-12 9.320E-12 THYROID 1.300E-13 1.127E-11 1.129E-11 2.480E-15-.OOOE+00 2.880E-10 6.210E-10 REMAINDER 1.220E-i3 1.091E-11 1.093E-11 2.400E-15-I.OD0E+00 2.270E-11 1.340E-10 EFFECTIVE 1.300E-13 1.150E-11 1.152E-11 2.530E-15-I.DO0E+00 3.550E-11 6.660E-11 SKIN(FGR) 1.870E-13 4.477E-11 4.485E-11 9.850E-15-1.OO0E+00 O.OOE+00 O.OOOE+00 1-135 GONADS 8.078E-14 3.113E-11 5.489E-11 1.599E-15-1.0OOE+00 1.700E-11 3.610E-11

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-8 BREAST 9.143E-14 2.971E-11 5.240E-11 1.526E-15-1.OOOE+00 2.340E-ll 3.850E-11 LUNGS 8.145E-14 2.886E-11 5.089E-11 1.482E-15-1.OOIE+00 4.410E-10 3.750E-11 RED MARR 8.054E-14 2.965E-11 5.228E-11 1.523E-15-I.CO0E+00 2.240E-11 3.650E-11 BONE SUR 1.184E-13 3.983E-11 7.024E-11 2.046E-15-I.OO0E+00 2.010E-11 3.360E-Il THYROID 8.324E-14 2.852E-11 5.030E-11 1.465E-15-1.OOE+00 8.460E-09 1.790E-08 REMAINDER 7.861E-14 2.883E-11 5.084E-11 1.481E-15-1.OI0E+00 4.700E-11 1.540E-10 EFFECTIVE 8.294E-14 2.989E-11 5.271E-I1 1.535E-15-I.OC0E+00 3.320E-10 6.080E-10 SKIN(FGR) 1.156E-13 9.826E-11 1.733E-10 5.047E-15-I.C00E+00 0.OOOE+00 0.,OE+00 Xe-133 GONADS 1.610E-15 1.465E-12 2.052E-11 5.200E-17-I. OE+00 O.OOE+00 0.OOOE+00 BREAST 1.960E-15 1.505E-12 2.107E-11 5.340E-17-I.OOE+00 0.Q00E+00 O.0OOE+00 LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-.O0OE+00 0.000E+00 O.OOE+00 REDBMARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+00 O.OOE+00 O.00E+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.OOE+00 O.OO0E+00 O.OOE+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-I.CO0E+00 O.OE+00 0.000E+00 REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-I.CO0E+00 O.OOOE+00 0.OOOE+00 EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-I.C00E+00 0.OOE+00 D.OO0E+00 SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.OD0E+00 O.00E+00 O.O0E+00 Xe-133m GONADS 1.610E-15 1.465E-12 2.052E-11 5.200E-17-1.OOOE+00 0.OOE+00 O.0OOE+00 BREAST 1.960E-15 1.505E-12 2.107E-11 5.340E-17-I.CO0E+00 O.OOE+00 O.000E+00 LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-.OO0E+00 O.OOE+00 O.000E+00 RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OO0E+00 0.OOOE+00 D.OOOE+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-I.DC0E+00 O.OOE+00 O.OO0E+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OO0E+00 0.OO0E+00 O.00E+00 REMAINDER 1.240E-15 1.042E-12 1.460E-II 3.700E-17-1.OOOE+00 .OC0E+00 O.000E+00 EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-I.C00E+00 D.C00E+00 0.000E+00 SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-I.C00E+00 O.OOE+00 O.OOE+00 Xe-135 GONADS 1.170E-14 5.455E-12 1 194E-11 2.530E-16-I.C00E+00 0.OC0E+00 O.OOE+00 BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-.OOE+00 0.D00E+00 .000E+00 LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.OO0E+00 O.00E+00 .000E+00 RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-i.OO0E+00 0.COE+00 O.OOOE+00 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.CC0E+00 O.OOE+00 .0 0E+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-.0OO0E+00 O.CC0E+00 0.OO0E+00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.24DE-16-I.CO0E+00 0.000E+00 O.OOE+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-I.0OOE+00 0.C00E+00 O.OOE+00 SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-.OOOE+00 0.000E+00 0.COE+00 Xe-135m GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.000E+00 0.OOE+00 0.O00E+00 BREAST l,330E-14 5.325E-12 1.166E-11 2.470E-16-1.OOE+00 O.OOOE+00 0. OE+00 LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.0OOE+00 O.00E+00 .000E+00 RED MARR 1.070E-14 4.959E-12 1.086E-II 2.300E-16-1.C00E+00 0.000E+00 .OOOE+00 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.000E+00 0.OC0E+00 O.OOE+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.OOE+00 C.OD0E+00 0.OOOE+00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.OOOE+00 0.0OOE+00 O.OOE+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.000E+00 O.OOE+00 .000E+00 SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-1.000E+00 O.OOE+00 D.DO0E+00 Xe-137 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.000E+00 O.000E+00 0.COE+00 BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.OO0E+00 O.OE+00 0.COE+00 LUNGS 1.130E-14 4.959E-12 1.086E-ll 2.300E-16-1.OOOE+00 O.OOOE+00 0.OOOE+00 RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-1.000E+00 O.0O0E+00 0.C00E+00 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.0OOE+00 0.000E+00 O.OOE+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.C00E+00 0.,O0E+00 O.OOE+00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.OC0E+00 0.OOOE+00 O.OOE+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.OC0E+00 C.OOE+00 0.C00E+00 SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-1.OOE+00 O.000E+00 0.CO0E+00 Xe-138 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.OOOE+00 0.0O0E+00 O.DOE+00 BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.OO0E+00 0.D00E+00 O.OOE+00 LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.DC0E+00 C.OO0E+00 0.OO0E+00 RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-1.OOOE+00 O.000E+00 0.0O0E+00

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-9 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-l.OOOE+00 0.00E+00 0.0OOE+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.O0OE+00 O.0OOE+00 0.OOE+D00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.000E+00 O.OOOE+00 0.OD0E+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.OOOE+00 O.OODE+00 O.OOE+00 SKIN(FGR) 3.120E-14 4..506E-11 9.867E-11 2.090E-15-l.OOE+00 O.000E+00 0.OOOE+00 Cs-134 GONADS 7.400E-14 4.607E-11 9.646E-10 1.600E-15-1.ODOE+00 1.300E-08 2.060E-08 BREAST 8.430E-14 4.406E-11 9.224E-10 1.530E-15-1.DOE+00 1.080E-08 1.720E-08 LUNGS 7.370E-14 4.204E-11 8.802E-10 1.460E-15-1.DOE+00 1.180E-08 1.760E-08 RED MARR 7.190E-14 4.262E-11 8.922E-D0 1.480E-15-1.O0OE+00 1.180E-08 1.870E-08 BONE SUR 1.200E-13 6.105E-11 1.278E-09 2.120E-15-1.0D0E+00 1.100E-08 1.740E-08 THYROID 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.DOE+00 1.11OE-08 1.760E-08 REMAINDER 7.060E-14 4.147E-11 8.681E-10 1.440E-15-1.OO0E+00 1.390E-08 2.210E-08 EFFECTIVE 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.DOOE+00 1.250E-08 1.980E-08 SKIN(FGR) 9.450E-14 6.249E-I1 1.308E-09 2.170E-15-1.OODE+00 0.DOOE+00 O.0D0E+00 Cs-136 GONADS 1.040E-13 6.223E-11 1.102E-09 2.180E-15-I.ODDE+00 1.880E-09 3.040E-09 BREAST 1.180E-13 5.966E-11 1.056E-09 2.090E-15-I.ODOE+00 1.670E-09 2.650E-09 LUNGS 1.040E-13 5.710E-11 1.011E-09 2.DOOE-15-1.OOOE+00 2.320E-09 2.620E-09 RED MARR 1.010E-13 5.824E-11 1.031E-09 2.040E-15-.DOO0E+00 1.860E-09 2.950E-09 BONE SUR 1.660E-13 8.422E-11 1.491E-09 2.950E-15-.OOOE+00 1.700E-09 2.710E-09 THYROID 1.070E-13 5.852E-11 1.036E-09 2.050E-1571.C0DE+00 1.730E-09 2.740E-09 REMAINDER 9.950E-14 5.652E-11 1.001E-09 1.980E-15-I.OOOE+00 2.190E-09 3.520E-09 EFFECTIVE 1.060E-13 5.966E-11 1.056E-09 2.090E-15-I. O0E+00 1.980E-09 3.040E-09 SKIN(FGR) 1.250E-13 7.251E-11 1.284E-09 2.540E-15-.OOOE+00 O.0OOE+00 O.0OOE+00 Cs-137 GONADS 2.669E-14 1.669E-11 3.530E-10 5.840E-16-1.000E+00 8.760E-09 1.390E-08 BREAST 3.047E-14 1.596E-11 3.376E-10 5.585E-16-1.ODE+00 7.840E-09 1.240E-08 LUNGS 2.649E-14 1.517E-11 3.209E-10 5.309E-16-1.O00E+00 8.820E-09 1.270E-08 RED MARR 2.583E-14 1.542E-11 3.260E-10 5.394E-16-1.OOOE+00 8.300E-09 1.320E-08 BONE SUR 4.382E-14 2.238E-11 4.734E-10 7.832E-16-1.0OOE+00 7.940E-09 1.260E-08 THYROID 2.725E-14 1.588E-11 3.358E-10 5.556E-16-1.0O0E+00 7.930E-09 1.260E-08 REMAINDER 2.536E-14 1.490E-11 3.152E-10 5.215E-16-1.O0OE+00 9.120E-09 1.450E-08 EFFECTIVE 2.725E-14 1.585E-11 3.353E-10 5.546E-16-1.DOOE+00 8.630E-09 1.350E-08 SKIN(FGR) 4.392E-14 5.253E-11 1.110E-09 1.836E-15-1.OODE+00 0.000E+00 0.ODQE+00 Ba-137m GONADS 2.669E-14 1.669E-11 3.530E-l0 5.840E-16-1.DO0E+00 8.760E-09 1.390E-08 BREAST 3.047E-14 1.596E-11 3.376E-10 5.585E-16-1.OO0E+00 7.840E-09 1.240E-08 LUNGS 2.649E-14 1.517E-11 3.209E-10 5.309E-16-1.OO0E+00 8.820E-09 1.270E-08 RED MARR 2.583E-14 1.542E-11 3.260E-10 5.394E-16-1.DODE+00 8.300E-09 1.320E-08 BONE SUR 4.382E-14 2.238E-11 4.734E-10 7.832E-16-1.DOOE+00 7.940E-09 1.260E-08 THYROID 2.725E-14 1.588E-11 3.358E-10 5.556E-16-1.O00E+00 7.930E-09 1.260E-08 REMAINDER 2.536E-14 1.490E-11 3.152E-10 5.215E-16-1.ODDE+00 9.120E-09 1.450E-08 EFFECTIVE 2.725E-14 1.585E-11 3.353E-10 5.546E-16-1.OO0E+00 8.630E-09 1.350E-08 SKIN(FGR) 4.392E-14 5.253E-11 1.110E-09 1.836E-15-1.DO0E+00 0.000E+00 D.000E+00 Ba-139 GONADS 2.130E-15 3.368E-13 3.429E-13 4.790E-17-1.OOOE+00 2.560E-12 1.560E-12 BREAST 2.450E-15 3.297E-13 3.357E-13 4.690E-17-1.OOOE+00 2.460E-12 5.170E-13 LUNGS 2.030E-15 3.002E-13 3.057E-13 4.270E-17-1.000E+00 2.530E-10 3.890E-13 RED MARR 1.870E-15 2.932E-13 2.985E-13 4.170E-17-1.OOE+00 3.410E-12 8.590E-13 BONE SUR 5.290E-15 6.841E-13 6.965E-13 9.730E-17-1.DO0E+00 2.490E-12 4.380E-13 THYROID 2.130E-15 3.044E-13 3.D00E-13 4.330E-17-1.D0DE+00 2.400E-12 2.660E-13 REMAINDER 1.920E-15 2.932E-13 2.985E-13 4.170E-17-1.O00E+00 4.820E-11 3.570E-10 EFFECTIVE 2.170E-15 3.227E-13 3.286E-13 4.590E-17-1.OOE+00 4.640E-11 1.080E-10 SKIN(FGR) 6.160E-14 7.241E-11 7.373E-11 1.030E-14-1.ODOE+00 O.ODOE+00 O.0O0E+00 Ba-140 GONADS 8.410E-15 5.451E-12 9.607E-11 1.910E-16-1.OOOE+00 4.300E-10 9.960E-10 BREAST 9.640E-15 5.280E-12 9.305E-11 1.850E-16-1.O0DE+00 2.870E-10 1.590E-10 LUNGS 8.270E-15 4.852E-12 8.550E-11 1.700E-16-1.OOOE+00 1.660E-09 6.630E-11 RED MARR 7.930E-15 4.880E-12 8.601E-11 1.710E-16-I.O0OE+00 1.290E-09 4.390E-10 BONE SUR 1.550E-14 8.020E-12 1.413E-10 2.810E-16-1.000E+00 2.410E-09 5.530E-10 THYROID 8.530E-15 5.109E-12 9.003E-11 1.790E-16-1.DO0E+00 2.560E-10 5.250E-11 REMAINDER 7.890E-15 4.766E-12 8.399E-11 1.670E-16-1.OODE+00 1.410E-09 7.370E-09

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. A-0 EFFECTIVE 8.580E-15 5.137E-12 9.053E-11 1.800E-16-1.OOE+00 1.010E-09 2.560E-09 SKIN(FGR) 2.520E-14 5.565E-11 9.808E-10 1.950E-15-1.OOOE+00 O.OOE+00 D.OOOE+00 La-140 GONADS 1.140E-13 6.027E-11 4.425E-10 2.240E-15-1.0OOE+00 4.540E-10 1.340E-09 BREAST 1.290E-13 5.758E-11 4.228E-10 2.140E-15-1.0OOE+00 1.450E-10 1 800E-10 LUNGS 1.150E-13 5.596E-11 4.109E-10 2.080E-15-1.OOE+00 4.210E-09 4.010E-11 RED MARR 1.140E-13 5.731E-11 4.208E-10 2.130E-15-1.D0DE+00 2.140E-10 2.810E-10 BONE SUR 1.690E-13 7.776E-11 5.709E-10 2.890E-15-1.OOOE+00 1.410E-10 9.770E-11 THYROID 1.180E-13 5.462E-11 4.010E-10 2.030E-15-1.0OOE+00 6.870E-11 6.400E-12 REMAINDER 1.11OE-13 5.569E-11 4.089E-10 2.070E-15-1.OO0E+00 2.120E-09 6.260E-09 EFFECTIVE 1.170E-13 5.812E-I1 4.267E-10 2.160E-15-i.OOOE+00 1.310E-09 2.280E-09 SKIN(FGR) 1.660E-13 2.217E-10 1.628E-09 8.240E-15-1.000E+00 O.OOOE+00 O.ODOE+00 La-141 GONADS 2.330E-15 7.315E-13 9.675E-13 4.740E-17-1.OO0E+00 1.010E-11 3.770E-12 BREAST 2.640E-15 7.007E-13 9.267E-13 4.540E-17-1.000E+00 9.840E-12 7.070E-13 LUNGS 2.340E-15 6.713E-13 8.879E-13 4.350E-17-1.DD0E+00 6.460E-10 2.720E-13 RED MARR 2.310E-15 6.852E-13 9.063E-13 4.440E-17-1.DODE+00 2*930E-11 1.070E-12 BONE SUR 3.490E-15 9.923E-13 1.312E-12 6.430E-17-1.D00E+00 1.200E-10 6.060E-13 THYROID 2.390E-15 6.590E-13 8.716E-13 4.270E-17-1.OOOE+00 9.400E-12 5.290E-14 REMAINDER 2.260E-15 6.682E-13 8.838E-13 4.330E-17-1.OOE+00 2.280E-10 1.240E-09 EFFECTIVE 2.390E-15 7.007E-13 9.267E-13 4.540E-17-1.000E+00 1.570E-10 3.740E-10 SKIN(FGR) 6.580E-14 1.667E-10 2.204E-10 1.080E-14-1.O00E+00 0.000E+00 D.DO0E+00 La-142 GONADS 1.400E-13 1.978E-11 2.034E-11 2.540E-15-1.00DE+00 1.660E-11 6.990E-11 BREAST 1.570E-13 1.885E-11 1.938E-1I 2.420E-15-l.0O0E+00 1.130E-11 1.540E-11

-LUNGS 1.420E-13 1.846E-11 1.898E-11 2.370E-15-I.OOOE+00 3.010E-10 8.400E-12 RED MARR 1.420E-13 1.900E-11 1.954E-11 2.440E-15-1.OOE+00 1.360E-11 1.930E-11 BONE SUR 1.950E-13 2.484E-11 2.554E-11 3.190E-15-1.OOOE+00 1.110E-11 7.400E-12 THYROID 1.450E-13 1.768E-1I 1.818E-11 2.270E-15-1.000E+00 8.740E-12 1.160E-12 REMAINDER 1.380E-13 1.853E-11 1.906E-11 2.380E-15-1.DO0E+00 8.070E-11 5.200E-10 EFFECTIVE 1.440E-13 1.916E-11 1.970E-112.460E-15-1.O0OE+00 6.840E-11 1.790E-10 SKIN(FGR) 2.160E-13 9.111E-11 9.368E-I1 1.170E-14-1.O00E+00 D.0OOE+00 D.ODCE+00 Ce-141 GONADS 3.380E-15 2.213E-12 4.332E-11 7.710E-17-1.OOOE+00 5.540E-11 1.080E-10 BREAST 3.930E-15 2.170E-12 4.247E-11 7.560E-17-1.0O0E+00 4.460E-11 1.110E-11 LUNGS 3.170E-15 1.951E-12 3.820E-11 6.800E-177I.ODOE+00 1.670E-08 1.430E-12 RED MARR 2.830E-15 1.860E-12 3.641E-11 6.480E-17-1.ODOE+00 8.960E-11 3.390E-11 BONE SUR 9.410E-15 5.166E-12 1.011E-10 1.800E-16-1.OD0E+00 2.540E-10 2.300E-11 THYROID 3.350E-15 2.003E-12 3.922E-11 6.980E-17-1.OODE+00 2.550E-11 1.800E-13 REMAINDER 2.980E-15 1.894E-12 3.708E-11 6.600E-17-1.OO0E+00 1.260E-09 2.500E-09 EFFECTIVE 3.430E-15 2.118E-12 4.146E-11 7.380E-17-1.OD0E+00 2.420E-09 7.830E-10 SKIN(FGR) 1.020E-14 3.788E-12 7.416E-11 1.320E-16-1.OOE+00 0.OOOE+00 O.OD0E+00 Ce-143 GONADS 1.280E-14 7.900E-12 4.958E-11 2.980E-16-1.OD0E+00 7.530E-11 2.120E-10 BREAST 1.470E-14 7.688E-12 4.825E-11 2.900E-16-1.0OOE+00 1.660E-11 2.320E-11 LUNGS 1.230E-14 6.893E-12 4.325E-11 2.600E-16-1.0OOE+00 3.880E-09 3.820E-12 RED MARR 1.170E-14 6.787E-12 4.259E-11 2.560E-16-1.OOOE+00 2.960E-11 5.070E-11 BONE SUR 2.520E-14 1.323E-11 8.302E-11 4.990E-16-1.OOE+00 1.640E-11 1.610E-11 THYROID 1.280E-14 7.211E-12 4.525E-11 2.720E-16-1.0OOE+00 6.230E-12 4.350E-13 REMAINDER 1.170E-14 6.734E-12 4.226E-11 2.540E-16-1.O0DE+00 1.420E-09 3.890E-09 EFFECTIVE 1.290E-14 7.396E-12 4.642E-11 2.790E-16-1.OOE+00 9.160E-10 1.230E-09 SKIN(FGR) 3.960E-14 1.058E-10 6.638E-10 3.990E-15-1.OOE+00 O.OOOE+00 O.OOE+00 Ce-144 GONADS 2.725E-15 6.328E-13 1.319E-11 6.088E-17-1.OOE+00 2.390E-10 6.987E-11 BREAST 3.129E-15 6.274E-13 1.307E-11 5.922E-17-1.O0OE+00 3.480E-10 1.223E-11 LUNGS 2.639E-15 5.228E-13 1.089E-11 5.362E-17-1.O0OE+00 7.911E-07 6.551E-12 RED MARR 2.507E-15 4.755E-13 9.907E-12 5.247E-17-1.OOOE+00 2.880E-09 8.923E-11 BONE SUR 5.441E-15 i.646E-12 3.429E-11 1.127E-16-1.OOE+00 4.720E-09 1.280E-10 THYROID 2.753E-15 5.529E-13 1.152E-11 5.418E-17-1.OOOE+00 2.920E-10 5.154E-12 REMAINDER 2.534E-15 5.086E-13 1.060E-11 5.283E-17-1.00DE+00 1.910E-08 1.890E-08 EFFECTIVE 2.773E-15 5.909E-13 1.231E-ii 5.766E-17-1.OOOE+00 1.010E-07 5.711E-09 SKIN(FGR) 8.574E-14 7.648E-13 1.594E-11 i.250E-14-1.0O0E+00 O.OOE+00 0.OOE+00 Pr-143

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO.A-11 1 GONADS 2.130E-17 2.264E-14 4.032E-13 7.930E-19-1.OO0E+00 4.370E-18 8.990E-18 BREAST 2.550E-17 2.330E-14 4.149E-13 8.160E-19-1.OOOE+00 2.220E-18 1.090E-18 LUNGS 1.860E-17 1.642E-14 2.923E-13 5.750E-19-1.OOOE+00 1.330E-08 1.910E-19 RED MARR 1.620E-17 1.493E-14 2.659E-13 5.230E-19-1.OOOE+00 1.480E-11 1.030E-12 BONE SUR 5.930E-17 5.454E-14 9.711E-13 1.910E-18-1.OO0E+00 1.490E-11 1.030E-12 THYROID 2.050E-17 1.802E-14 3.208E-13 6.310E-19-1.OO0E+00 1.680E-18 2.660E-20 REMAINDER 1.760E-17 1.642E-14 2.923E-13 5.750E-19-1.O0OE+00 1.970E-09 4.220E-09 EFFECTIVE 2.100E-17 2.002E-14 3.564E-13 7.010E-19-1.OOOE+00 2.190E-09 1.270E-09 SKIN(FGR) 1.760E-14 5.711E-I1 1.017E-09 2.OOE-15-1.O00E+00 O.0OOE+00 D.OOE+00 Nd-147 GONADS 6.130E-15 4.218E-12 7.235E-11 1.480E-16-1.OOOE+00 8.410E-11 1.790E-10 BREAST 7.120E-15 4.132E-12 7.088E-11 1.450E-16-1.OO0E+00 3.450E-11 1.870E-11 LUNGS 5.820E-15 3.648E-12 6.257E-11 1.280E-16-1.OOOE+00 1.060E-08 2.440E-12 RED MARR 5.400E-15 3.505E-12 6.013E-11 l.230E-16-1.OODE+00 9.190E-11 5.050E-11 BONE SUR 1.320E-14 8.265E-12 1.418E-10 2.900E-16-1.OO0E+00 3.260E-10 2.220E-11 THYROID 6.120E-15 3.876E-12 6.648E-11 1.360E-16-1.OO0E+00 1.820E-11 2.640E-13 REMAINDER 5.530E-15 3.562E-12 6.l11E-11 1.250E-16-1.000E+00 1.760E-09 3.760E-09 EFFECTIVE 6.190E-15 3.961E-12 6.795E-11 1.390E-16-1.O00E+00 1.850E-09 1.180E-09 SKIN(FGR) 1.950E-14 3.135E-11 5.377E-10 1.100E-15-1.000E+00 O.00E+00 0.000E+00 Np-239 GONADS 7.530E-15 4.691E-12 4.380E-11 1.710E-16-1.OO0E+00 7.450E-11 1.620E-10 BREAST 8.730E-15 4.636E-12 4.329E-11 l.690E-16-1.ODOE+00 1.630E-11 1.720E-11 LUNGS 7.180E-15 4.115E-12 3.842E-11 l.500E-16-1.000E+00 2.360E-09 2.400E-12 RED MARR 6.500E-15 4.005E-12 3.740E-11 1.460E-16-1.000E+00 2.080E-10 4.660E-11 BONE SUR 2.O00E-14 1.001E-11 9.349E-11 3.650E-16-1.OO0E+00 2.030E-09 3.590E-11 THYROID 7.520E-15 4.197E-12 3.919E-11 1.530E-16-1.0O0E+00 7.620E-12 2.070E-13 REMAINDER 6.760E-15 4.005E-12 3.740E-11 1.460E-16-1.OO0E+00 9.590E-10 2.770E-09 EFFECTIVE 7.690E-15 4.471E-12 4.175E-11 1.630E-16-1.OO0E+00 6.780E-10 8.820E-10 SKIN(FGR) 1.600E-14 7.215E-12 6.737E-11 2.630E-16-1.000E+00 O.OOE+00 O.OOOE+00 Pu-238 GONADS 6.560E-18 4.291E-14 9.011E-13 1.490E-18-1.OOIE+00 1.040E-05 2.330E-09 BREAST 1.270E-17 5.558E-14 1.167E-12 1.930E-18-I.OOOE+00 4.400E-10 1.800E-13 LUNGS 1.060E-18 2.267E-15 4.759E-14 7.870E-20-I.OOOE+00 3.200E-04 8.640E-14 RED MARR 1.680E-18 5.587E-15 1.173E-13 1.940E-19-1.O0E+00 5.800E-05 1.270E-08 BONE SUR 9.300E-18 3.514E-14 7.378E-13 1.220E-18-l.OODE+00 7.250E-04 1.580E-07 THYROID 4.010E-18 9.792E-15 2.056E-13 3.400E-19-.O0OE+00 3.860E-10 7.990E-14 REMAINDER 1.990E-18 9.216E-15 1.935E-13 3.200E-19-1.OOOE+00 2.740E-05 2.180E-08 EFFECTIVE 4.880E-18 2.413E-14 5.068E-13 8.380E-19-I.DO0E+00 7.790E-05 1.340E-08 SKIN(FGR) 4.090E-17 2.776E-13 5.830E-12 9.640E-18-I.OO0E+00 O.OOOE+00 0.OD0E+00 Pu-239 GONADS 4.840E-18 1.768E-14 3.713E-13 6.140E-19-1.ODE+00 1.200E-05 2.640E-09 BREAST 7.550E-18 2.238E-14 4.699E-13 7.770E-19-l.OO0E+00 3.990E-10 1.210E-13 LUNGS 2.650E-18 2.267E-15 4.760E-14 7.870E-20-1.DO0E+00 3.230E-04 7.890E-14 RED MARR 2.670E-18 3.456E-15 7.258E-14 l.200E-19-l.OO0E+00 6.570E-05 1.410E-08 BONE SUR 9.470E-18 1.673E-14 3.514E-13 5.810E-19-I.OO0E+00 8.210E-04 1.760E-07 THYROID 3.880E-18 5.126E-15 1.077E-13 l.780E-19-I.OOOE+00 3.750E-10 7.500E-14 REMAINDER 2.860E-18 4.838E-15 1.016E-13 1.680E-19-1.OOOE+00 3.020E-05 2.120E-08 EFFECTIVE 4.240E-18 1.057E-14 2.220E-13 3.670E-19-1.00DE+00 8.330E-05 1.400E-08 SKIN(FGR) 1.860E-17 1.057E-13 2.220E-12 3.670E-18-1.OO0E+00 0.D0DE+00 0.C00E+00

SCALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. B-I I ATTACHMENT B OC RADTRAD FILE RADTRAD Version 3.03 (Spring 2001) run on 10/05/2007. at 10:34:15

1. 1. 1. 1. 4#############

File information Plant file = C:\Program Files\radtrad3.03\OC AST\FHA 2007\FHA source release.psf Inventory file = c:\program files\radtrad3.03\defaults\ocfhaikr.nif Release file = c:\program files\radtrad3.03\oc ast\oc fha.rft Dose Conversion file = c:\program files\radtrad3.03\oc ast\oc60.inp Y

44444 4444 44444 4 4 4 44444 4 4 44444 4 44 4 4 44 4 4 4 4 4 4 4 44 4 4 44 4 4 4 4 4 4 44444 4444 4444 4 4 4 4 4 4 4 4~t444 4 44 4 4 *4 4 4 4 4 4 4 44 4 4 44 4 4 4 4 4444 4 44 44 Racdtrad 3.03 4/15/2001 Nuclide Inventory File:

c:\program files\radtrad3.03\defaults\ocfhaikr.nif Plant Power Level:

1.1310E+01 Compartments:

3 Compartment 1:

Refuel Floor Airspace 3

1.0000E+02 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.7500E+04 0

0

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. B-2 1 0

0 0

Pathways:

3 Pathway 1:

Refuel Floor Airspace to Environment 2

2 2

Pathway 2:

Environment to Control Room 2

3 2

Pathway 3:

Control Room to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OO00E+00 c:\program files\radtrad3.03\oc ast\oc60.inp c:\program files\radtrad3.03\oc ast\oc fha.rft 2.4000E+01 1

0.0000E+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:

0 O.000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

I CALCULATION NO. C-1 302-822-E310-082 I REV. No. 0 II PAGE PAGE NO.

NO. B-3 II I CALCULATION NO. C-i 302-822-E310-082 I REV. No. 0 B-3 0

0 0

Pathways:

3 Pathway 1:

0 0

0 1

2 2.4000E+01 1.0000E+03 o. OCCE+CC o . CCCE+0C O . CCOE+00

7. 4400E+02 o.0000E+00 o. CCOE+CC o .COCOE+0C o.OOCCE+CO 0

0 0

0 Pathway 2:

0 0

0 1.

2

2. 4000E+01 1.4000E+04 O. CCCE+CC o . OOCE+CO o. CCCE+OC

7. 4400E+02 O.0000E+00 o. CCCE+CC o . CCCCEi-C o. CCCE+CC 0

0 0

0 Pathway 3:

0 0

0 1

2

2. 4000E+01 2.0000E+03 o. CCCE+CO o. CCCE+CO C.0000E+00

7. 4400E+02 0.0O00E+00 o. CCCE+00 o. OOCE+CO 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 IPAGE NO. B-4 I 2

1 2

2.4000E+01 1.4100E-03 7.4400E+02 O.0OOOE+00 1

4 2.4000E+01 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 O.O0OOE+00 0

Location 2:

Low Population Zone 2

1 2

2.4000E+01 1.3500E-04 7.4400E+02 O.OOOOE+00 1

4 2.4000E+01 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 O.OOOOE+00 0

Location 3:

Control Room 3

0 1

2 2.4000E+01 3.5000E-04 7.4400E+02 0.OOOOE+00 1

4 2.4000E+01 1.0OOOE+00 4.8000E+01 6.OOOOE-01 1.2000E+02 4.OOOE-01 7.4400E+02 0.0000E+00 Effective Volume Location:

1 6

2.4000E+01 6.7500E-03 2.6000E+01 6.7500E-03 3.2000E+01 6.7500E-03 4.8000E+01 6.7500E-03 1.2000E+02 6.7500E-03 7.4400E+02 0.0OOOE+00 Simulation Parameters:

1 2.4000E+01 0.OOOE+00 Output Filename:

C:\Program Files\radtrad3.o270 1

1 1

End of Scenario File

I CALCULATION NO. C-1 302-822-E310-082 REV. No. 0 I PAGE NO. B-5 I RADTRAD Version 3.03 (Spring 2001) run on 10/05/2007 at 10:34:15 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 1.1310E+01 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Refuel Floor Airspace Compartment volume = 1.OOOOE+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Refuel Floor Airspace to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Refuel Floor Airspace to Environment Inlet Pathway Number 3: Control Room to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume = 2.7500E+04 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Total number of pathways = 3

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. B-6 I RADTRAD Version 3.03 (Spring 2001) run on 10/05/2007 at 10:34:15

1. 1. 1. 1. S###########

Scenario Description Time between shutdown and first release 2.4000E+01 (Hours)

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000001 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 5.0000E-02 0 OOOOE+00 0 OOOOE+00 1. 097E+00 IODINE 2.5000E-04 0 OOOOE+00 0 OOOOE+00 1.329E-03 CESIUM 0.OOOOE+00 0.OOOOE+00 0. 0000E+00 0. OOOE+00 TELLURIUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0. OOOE+00 STRONTIUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0. OOOE+00 BARIUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0. OOOE+00 RUTHENIUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0.OOOE+00 CERIUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0.OOOE+00 LANTHANUM 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0. OOOE+00 Inventory Power = 11. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-83m 1 4.150E+03 6. 696E+03 7. 480E-15 0. OOOE+00 0. OOOE+00 Kr-85m 1 6.940E+03 1. 613E+04 7. 480E-15 0. OOOE+00 0. OOOE+00 Kr-85 1 6.450E+02 3. 386E+08 1 .190E-16 0. OOOE+00 0. OOOE+00 Kr-87 1 1.290E+04 4. 578E+03 4. 120E-14 0. OOOE+00 0. OOOE+00 Kr-88 1 1.830E+04 1. 022E+04 0 OOOE+00 0 00.OE+00 0.OOOE+00 Kr-89 1 3.980E+04 1. 896E+02 9. 7 90E-14 0. OOOE+00 0.OOOE+00 1-131 2 5 .020E+04 6. 947E+05 1. 670E-14 5.730E-11 8.030E-I1 1-132 2 3 .660E+04 8.280E+03 1. 050E-13 1.240E-11 3.780E-11 1-133 2 5 .180E+04 7.488E+04 2. 730E-14 2. 520E-11 5.OOOE-If 1-134 2 5. 6OOE+04 3. 156E+03 1.220E-13 5. 310E-12 2.270E-11 1-135 2 4.820E+04 2. 380E+04 7. 861E-14 2. OlE-1l 4.700E-I1 Xe-133 1 5.230E+04 4.532E+05 1. 240E-15 0. OOOE+00 0. OOOE+00 Xe-133m '1 l.380E+03 1. 927E+05 1. 240E-15 0 . OOOE+00 0.OOOE+00 Xe-135 1 1.810E+04 3. 272E+04 1080E-14 0. OOOE+00 0. OOOE+00 Xe-135m 1 1 .560E+04 9. 180E+02 1. 080E-14 0. OOOE+00 0. OOOE+00 Xe-137 1 5.100E+04 2. 304E+02 1.080E-14 0. OOOE+00 0. OOOE+00 Xe-138 1 4. 780E+04 8.520E+02 1. 080E-14 0. OOOE+00 0. OOOE+00 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Kr-89 Sr-89 1.00 none 0.00 none 0.00 Sr-90 Y-90 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.00 none 0.00 none 0.00 Y-93 Zr-93 1.00 none 0.00 none 0.00 Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. B-7 I Tc-99m Tc-99 1.00 none 0.00 none 0. 00 Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 1-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 1-129 0.35 none 0.00 Te-131m Te-131 0.22 1-131 0.78 none 0.00 Te-132 1-132 1.00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 1-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1.00 none 0.00 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 0.99 Cs-135 0.00 none 0.00 Xe-137 Cs-137 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La-140 1.00 none 0.00 none 0.00 La-141 Ce-141 1.00 none 0.00 none 0.00 Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0 *00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-2 39 U-235 1.00 none 0.00 none 0.00 Iodine fractions Aerosol = 0.OOOOE+00 Elemental = 9.7000E-01 Organic - 3.OOOOE-02 COMPARTMENT DATA Compartment number 1: Refuel Floor Airspace Compartment number 2: Environment Compartment number 3: Control Room PATHWAY DATA Pathway number 1: Refuel Floor Airspace to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%.)

(cfm) Aerosol Elemental Organic 2.4000E+01 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.4400E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate FilterEfficiencies (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 1.4000E+04 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.4400E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Control Room to Environment

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO.B-8 Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 2.OOOE+03 0.0O00E+00 0.OOOE+00 0.OOOOE+00 7.4400E+02 0.0O00E+00 0.OOOE+00 0.0000E+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m^-3) 2.4000E+01 1.4100E-03 7.4400E+02 0.OOOE+00 Location Breathing .Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 2.4000E+01 3.5000E-04 3.2000E+01 1.80O0E-04

4. 8000E+01 2.3000E-04 7.4400E+02 0.0000E+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m^-3)

2. 4000E+01 1.3500E-04 7.4400E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3 ** se(c^-l) 2.4000E+01 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 o.0000E+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/Q (s

m^-3) 2.4000E+01 6.7500E-03

2. 6000E+01 6.7500E-03 3.2000E+01 6.7500E-03

4. 8000E+01 6.7500E-03 1.2000E+02 6.7500E-03 7.4400E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l)

2. 4000E+01 3.5000E-04 7.4400E+02 0.0000E+00 Ldcation Occupancy Factor Data Time (hr) Occupancy Factor 2.4000E+01 1.0000E+00

4. 8000E+01 6.OOO0E-01 1.2000E+02 4. 0000E-01 7.4400E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. B-9 RADTRAD Version 3.03 (Spring 2001) run on 10/05/2007 at 10:34:15

1. 1. 1. ti

it it####ti ###titi

it it#tt##

it it it it it it it it it it S it it it it it it it it it it i it it it ititt it it it it it it it it it it it it S it it it it it it it

1. 1. i# #i### # #

Dose Output

1. 1. 1. 1. 4#0######################################

Detailed model information at time (H) 24.0000 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1266E-04 5.7155E-06 2.2227E-04 Accumulated dose (rem) 2.1266E-04 5.7155E-06 2.2227E-04 11 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0361E-05 5.4723E-07 2.1281E-05 Accumulated dose (rem) 2. 0361E-05 5.4723E-07 2.1281E-05 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.1962E-10 4.1788E-10 1.1224E-09 Accumulated dose (rem) 4.1962F-10 4.1788E-10 1.1224E-09 Detailed model information at time (H) = 32.0000 Exclusion Area Boundary Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.0875E-01 1.9049E-02 7.4079E-01 Accumulated dose (rem) 7.0896E-01 1.9055E-02 7 .4101E-01 Low Population Zone Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.7859E-02 1.8239E-03 7.0926E-02 Accumulated dose (rem) 6.7879E-02 1.8244E-03 7.0948E-02 Control Room Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) 5. 3995E-01 5. 4689E-01 1.4548E+00 Accumulated dose (rem) 5.3995E-01 5.4689E-01 1.4548E+00 Detailed model information at time (H) 48.0000

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO.B-IO 1 Exclusion Area Boundary Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 7.0896E-01 1.9055E-02 7. 4101E-01 Low Population Zone Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 6.7879E-02 1.8244E-03 7.0948E-02 Control Room Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 2. 7642E-16 3. 7708E-16 8 .4693E-16 Accumulated dose (rem) 5.3995E-01 5. 4689E-01 1.4548E+00 Detailed model information at time (H) = 120.0000 Exclusion Area Boundary Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 7.0896E-01 1.9055E-02 7.4101E-01 Low Population Zone Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem)* 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Accumulated dose (rem) 6.7879E-02 1.8244E-03 7.0948E-02 Control Room Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0003E-46 2. 0810E-46 4.0399E-46 Accumulated dose (rem) 5.3995E-01 5.4689E-01 1.4548E+00 Detailed model information at time (H) = 744.0000 Exclusion Area Boundary Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 7.0896E-01 1.9055E-02 7.4101E-01 Low Population Zone Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 6.7879E-02 1.8244E-03 7.0948E-02 Control Room Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1475-183 3.4846-183 6.0564-183 Accumulated dose (rem) 5.3995E-01 5.4689E-01 1.4548E+00 837 1-131 Summary

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. B-li I

Refuel Floor Airspace Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 24.000 1. 3070E+02 3.9215E-02 1. 7489E-03 24.401 5.4979-103 1.3071E+02 1. 0214E+00 24.701 3.6873-181 1.3071E+02 2.7554E-01 25.001 2.4730-259 1.3071E+02 7. 4334E-02 25.301 0 OOOOE+00 1.3071E+02 2. 0054E-02 25.601 0 OOOOE+00 1.3071E+02 5. 4099E-03 25.901 0.OOOOE+00 1.3071E+02 1. 4595E-03 26.201 0.OOOOE+00 1.3071E+02 3. 9373E-04 26.501 0.OOOOE+00 1.3071E+02 1. 0622E-04 26..801 0.OOOOE+00 1.3071E+02 2. 8655E-05 27.101 0.OOOOE+00 1.3071E+02 7.7303E-06 27.401 0.OOOOE+00 1.3071E+02 2. 0854E-06 27.701 0.OOOOE+00 1.3071E+02 5. 6260E-07 28.001 0.OOOOE+00 1.3071E+02 1. 5178E-07 28.301 0.OOOOE+00 1.3071E+02 4. 0945E-08 28.601 0.OOOOE+00 1. 3071E+02 1 1046E-08 28.901 0.OOOOE+00 1.3071E+02 2. 9799E-09

29. 201 0.OOOOE+00 1.3071E+02 8. 0390E-10 29.501 0.OOOOE+00 1.3071E+02 2. 1687E-10 29.801 0.OOOOE+00 1.3071E+02 5. 8507E-11

30. 101 0.OOOOE+00 1.3071E+02 1. 5784E-I1 30.401 0.OOOOE+00 1.3071E+02 4.2580E-12 30.701 0.OOOOE+00 1.30ý1E+02 1.1487E-12 31.001 0.OOOOE+00 1.3071E+02 3.0989E-13 31.301 0.OOOOE+00 1. 3071E+02 8.3601E-14 31.601 0.OOOOE+00 1.3071E+02 2.2553E-14 31.901 0.OOOOE+00 1. 3071E+02 6.0843E-15 32.000 0.OOOOE+00 1.3071E+02 3.9410E-15 32.300 0.OOOOE+00 1. 3071E+02 1.0632E-15

32. 600 0.000OE+00 1.3071E+02 2. 8682E-16

32. 900 0.OOOOE+00 1.3071E+02 7 .7376E-17 33.200 0.OOOOE+00 1.3071E+02 2.0874E-17

33. 500 0.OOOOE+00 1.3071E+02 5.6313E-18 33.800 0.OOOOE+00 1.3071E+02 1.5192E-18 34.100 0.OOOOE+00 1. 3071E+02 4. 0984E-19 34.400 0.OOOOE+00 1. 3071E+02 1.1056E-19 48.000 0.OOOOE+00 1.3071E+02 1.7742E-45 120.000 0.OOOOE+00 1.3071E+02 4.8892-182 744.000 0.OOOOE+00 1.3071E+02 0.OOOOE+00 Cumulative Dose S~ummary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 24.000 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 24.401 1.9055E-02 7.14101E-01 1.8244E-03 7.0948E-02 4.3561E-01 1.1630E+00 24.701 1.9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5. 1716E 7 01 1. 3775E+00 25.001 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5.3894E-01 1.4343E+00 25.301 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5.4476E-01 1 4493E+00 25.601 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4632E-01 1. 4533E+00 25.901 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4674E-01 1. 4544E+00 26.201 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4685E-01 1. 4547E+00 26.501 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4688E-01 1. 4548E+00 26.'801 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4689E-01 1. 4548E+00 27.101 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5.4689E-01 1. 4548E+00 27.401 1.9055E-02 7.4101E-01 1. 8244E-03 7.0948E-02 5. 4689E-01 1. 4548E+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 1 PAGE NO. B- 12 I CACLTO O - 0-2-3002 I RE.N.0I PAEOB1 27.701 1. 9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 28.001 1 .9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 28.301 1.9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 28.601 1 .9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 28.901 1 .9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 29.201 1. 9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00

29. 501 1. 9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 29.801 1. 9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 30.101 1 .9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 30.401 1 .9055E-02 7 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 30.701 1 .9055E-02 7 .4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 31.001 1 .9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 31.301 1 .9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 31.601 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 31.961 1.9055E-02 7 4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 32.000 1. 9055E-02 7.4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 32.300 1. 9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02. 5. 4689E-01 1.4548E+00

32. 600 1. 9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00

32. 900 1 .9055E-02 7 4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 33.200 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5 .4689E-01 1.4548E+00 33.500 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5. 4689E-01 1.4548E+00 33.800 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00 34.100 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00 34 .400 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00 48.000 1.9055E-02 7 4101E-01 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00 120.000 1.9055E-02 7. 4101E-01 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00 744.000 1.9055E-02 7.4101E=01l 1.8244E-03 7.0948E-02 5.4689E-01 1.4548E+00

1. 1. 1. 1. W##################################################

Worst Two-Hour Doses

1. 1. 1. 1. 4##4##4#####4###################4#0#4#444##4#4#4#######4##

Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 24.0 7.0896E-01 1.9055E-02 7.4101E-01

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-iI ATTACHMENT C .NIF FILE Nuclide Inventory Name:

OC general Power Level:

0 1000E+01 Nuclides:

60 Nuclide 001:

Kr-83m 1

0.6696E+04 0.8300E+02 0 . 4150E+04 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

Kr-85m 1

0.1612800000E+05 0.8500E+02

6. 94E+03 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-85 1

0.338613048E+09 0.8500E+02 6.45E+02 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-87 1

0.4578000000E+04 0.8700E+02 1.29E+04 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

Kr-88 1

0.1022400000E+05 0.8800E+02 1.83E+04 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

Kr-89 1

0.1896E+03 0.8900E+02

3. 98E+04 Sr-89 0.1000E+01 none 0.OOOOE+00

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. C-2 none 0.OOOOE+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02

0. 403E+02 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 3.99E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 6.12E+02 Y-90 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05

0. 9100E+02 1.75E+04 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.OOOOE+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 2.61E+04 Y-92 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 3.42E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 013:

Y-91 9

0.5055264000E+07

0. 9100E+02

3. 27E+04 none 0.OOOOE+00 none 0.0000E+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-3 I none o.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 3.37E+04 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 3.87E+04 Zr-93 0.1000E+'01 none 0.OOOOE+'O0 none 0.0000E+'O0 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 4.42E+04 Nb-95m 0.7000E-' 02 Nb-95 0.9900E+'00 none 0.0000E+'00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02

4. 37E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.OOOOE+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 4.46E+04 none 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02

4. 70E+04 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none 0.OOOOE+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 4.11E+04 Tc-99 0.1000E+01 none 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-4 I none 0.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07

0. 1030E+03 3.98E+04 Rh-103m 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 2.57E+04 Rh-105 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.41E+04 Rh-106 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 2 .49E+04 none 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 2.33E+03 Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.OOOOE+00 Nuclide 026:

Sb-129 4

0.1555200000E+05

0. 1290E-03 0.803E+04 Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.0000E+00 Nuclide 027:

Te-127 4

0.3366000000E+05

0. 1270E+03 2.32E+03 none 0.0000E+00 none 0.0000E+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 PI IPAGE NO. C-5 none O.OOOOE+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 3.12E+02 Te-127 0.9800E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 7.93E+03 1-129 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 1.21E+03 Te-129 0.6500E+00 1-129 0.3500E+00 none 0:OOOOE+00 Nuclide 031:

Te-131m 4

0.1080000000E+06

0. 1310E+03 3.77E+03 Te-131 0.2200E+00 1-131 0.7800E+00 none 0.OOOOE+00 Nuclide 032:

Te-132 4

0.2815200000E+06

0. 1320E+03 3.60E+04 1-132 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03

5. 02E+04 Xe-131m 0.1100E-01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 034:

1-132 2

0.8280000000E+04

0. 1320E+03

3. 66E+04 none 0.OOOOE+00.

none 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-6 I none 0.0000E+00 Nuclide 035:

1-133 2

0.7488000000E+05 0.1330E+03 5.18E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nuclide 036:

1-134 2

0.3156000000E+04

0. 1340E+03

5. 60E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03 4 . 82E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 5.23E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 039:

Xe-133m 1

0.1926720000E+06 0.1330E+03 1.38E+03 Xe-133 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 040:

Xe-135 1

0.3272400000E+05 0.1350E+03 1.81E+04 Cs-135 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 041:

Xe-135m 1

0.91800000E+03 0.1350E+03

1. 56E+04 Xe-135 0.9940E+00 Cs-135 0.6000E-03

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-7 I none O.0000E+00 Nuclide 042:

Xe-137 1

0.230400000E+03

0. 1370E+03 5.10E+04 Cs-137 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 043:

Xe-138 1

0.85200000E+03 0.1380E+03 4.78E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 044:

Cs-134 3

0.6507177120E+08

0. 1340E+03 4.83E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 045:

Cs-136 3

0.1131840000E+07 0.1360E+03 1.39E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 046:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.56E+03 Ba-137m 0.9500E+00

.none 0.0000E+00 none 0.0000E+00 Nuclide 047:

Ba-137m 3

0.15300000E+03 0.1370E+03 1.81E+03 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 048:

Ba-139 6

0.4962000000E+04

0. 1390E+03 4.61E+04 none 0.OOOOE+00 none 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C-8 I none o.OOOOE+00 Nuclide 049:

Ba-140 6

0.1100736000E+07

0. 1400E+03

4. 51E+04 La-140 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 050:

La-140 9

0.1449792000E+06 0.1400E+03

4. 63E+04 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 051:

La-141 9

0.1414800000E+05 0.1410E+03 4.26E+04 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 052:

La-142 9

0.5550000000E+04 0.1420E+03

4. 12E+04 none 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 053:

Ce-141 8

0.2808086400E+07 0.1410E+03

4. 31E+04 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 054:

Ce-143 8

0.1188000000E+06 0.1430E+03

3. 98E+04 Pr-143 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 055:

Ce-144 8

0.2456352000E+08

0. 1440E+03 3.48E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00

I CALCULATION NO. C-1 302-822-E310-082 I REV. No. 0 I PAGE NO. C-9 I none O.OOOOE+00 Nuclide 056:

Pr-143 9

0.1171584000E+07 0.1430E+03,

3. 97E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 057:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.68E+04 Pm-147 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 058:

Np-239 8

0.2034720000E+06 0.2390E+03

5. 07E+05 Pu-239 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 059:

Pu-238 8

0.2768863824E+l0 0.2380E+03 1.04E+02 U-234 0.1000E+01 none 0.0000E+00 none 0.0000E+00, Nuclide 060:

Pu-239 8

0.7594336440E+12 0.2390E+03 1.43E+01 U-235 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 End of Nuclear Inventory File File ocesf.nif Nuclide Inventory Name:

OC esf Power Level:

0.1000E+01 Nuclides:

60 Nuclide 001:

Kr-83m 1

0.6696E+04 0.8300E+02 0.0000E+00

[CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGE NO. C- 10 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 002:

Kr-85m 1

0.1612800000E+05 0.8500E+02 0.0000E+00 Kr-85 0.2100E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 003:

Kr-85 1

0.338613048E+09 0.8500E+02 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-87 1

0.4578000000E+04 0.8700E+02 0.OOOOE+00 Rb-87 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 005:

Kr-88 1

0.1022400000E+05 0.8800E+02 O.OOOOE+00 Rb-88 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 006:

Kr-89 1

0.1896E+03 0.8900E+02 0.OOOOE+00 Sr-89 0.1000E+01 none 0.OOOOE+00 none 0.0.OOOE+00 Nuclide 007:

Rb- 86 3

0.1612224000E+07 0.8600E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 REV. No. 0 I PAGE NO. C-Il I none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 0.0000E+00 Y-90 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05

0. 9100E+02 0.0000E+00 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.0000E+00 Nuclide 011:

Sr-92 5

0.9756000000E+04

,0.9200E+02 0.0000E+00 Y-92 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Y-90, 9

0.2304000000E+06 0.9000E+02 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Y-91 9

0.5055264000E+07

0. 9100E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO.C-12 1 Zr-93 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 016:.

Zr-95 9

0.5527872000E+07 0.9500E+02 0.OOOOE+00 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none 0.OOOOE+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 0.0000E+00 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 0.0000E+00 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none 0.0000E+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 0.0000E+00 Tc-99 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 021:

Ru-103 7

0.3393792000E+07

0. 1030E+03 0.0000E+00 Rh-103m .0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 REV. No. 0 I PAGE NO. C-13 I Rh-105 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 0.OOOOE+00 Rh-106 0.1000E+01 none, 0.0000E+00 none 0.OOOOE+00 Nuclide 024:

Rh-105 7

0 .1272960000E+06 0.1050E+03 0.0000E+00.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 0.0000E+00 Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.0000E+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 0.0000E+00 Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.0000E+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 028:

Te-127m 4

0.9417600000E+07

0. 1270E+03 0.0000E+00 Te-127 0.9800E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04

0. 1290E+03 0.0000E+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO.C-14 I 1-129 0.1000E+01 none O.OOOOE+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.12 90E+03 o.0000E+00 Te-129 0.6500E+00 1-129 0.3500E+00 none 0.0000E+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 0.OOOOE+00 Te-131 0.2200E+00 1-131 0.7800E+00 none 0.0000E+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 0.0000E+00 1-132 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 033:

1-131 2,

0.6946560000E+06

0. 1310E+03 5.02E+04 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 034:

1-132 2

0.8280000000E+04 0.1320E+03 7.32E+04 none 0.0000E+ 00 none 0.0000E+ 00 none 0.0000E+ 00 Nuclide 035:

1-133 2

0.7488000000E+05

0. 1330E+03 1.04E+05 Xe-133m 0.2900E- 01.

Xe-133 0.9700E+ 00 none 0.0000E+ 00 Nuclide 036:

1-134 2

0.3156000000E+04

0. 1340E+03 1.12E+05

CALCULATION NO. C-1302-822-E310-082 REV. No. 0 PAGENO. C-15 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03

9. 64E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.OOOOE+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 039:

Xe-133m 1

0.1926720000E+06 0.1330E+03 0.0000E+00 Xe-133 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 040:

Xe-135 1

0.3272400000E+05 0.1350E+03 0.0000E+00 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 041:

Xe-135m 1

0.91800000E+03 0.1350E+03 0.OOOOE+00 Xe-135 0.9940E+00 Cs-135 0.6000E-03 none 0.OOOOE+00 Nuclide 042:

Xe-137 1

0.230400000E+03 0.1370E+03 0.OOOOE+00 Cs-137 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 043:

Xe-138 1

0.85200000E+03 0.1380E+03 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 j REV. No. 0 I PAGE NO. C-16 I none 0.OOOOE+00 none 0.O000E+00 none O.OOOOE+00 Nuclide 044:

Cs-134 3

0.6507177120E+08

0. 1340E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 045:

Cs-136 3

0.1131840000E+07

0. 1360E+03 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 046:

Cs-137 3

0.9467280000E+09

0. 1370E+03 0.0000E+00 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 047:

Ba-137m 3

0.15300000E+03

0. 1370E+03 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 048:

Ba-139 6

0.4962000000E+04 0.1390E+03 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 049:

Ba-140 6

0.1100736000E+07 0.1400E+03 0.0000E+00 La-140 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 050:

La-140 9

0.1449792000E+06

0. 1400E+03 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO.C-17 I none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 051:

La-141 9

0.1414800000E+05 0.1410E+03 0.0000E+00 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 052:

La-142 9

0.55500000000E+04

0. 1420E+03 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 053:

Ce-141 8

0.2808086400E+07 0.1410E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 054:

Ce-143 8

0.1188000000E+06 0.1430E+03 0.OOOOE+00 Pr-143 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 055:

Ce-144 8

0.2456352000E+08

0. 1440E+03 0.OOOOE+00 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.OOOOE+00 Nuclide 056:

Pr-143 9

0.I171584000E+07

0. 1430E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 057:

Nd-147 9

0.9486720000E+06 0.1470E+03 0.OOOOE+00

I CALCULATION NO. C-1302-822-E310-082 I REV. No. 0 I PAGE NO. C- 18 I ACLTO O -I 3282E1-8 I E.N.0 AEOC1 I Pm-147 0.1000E+01 none 0.0000E+00 none O.0000E+00 Nuclide 058:

Np-239 8

0.2034720000E+06 0.2390E+03 0.0000E+00 Pu-239 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 059:

Pu-238 8

0.2768863824E+i0 0.2380E+03 0.0000E+00 U-234 0.1000E+01 none 0.0000E+00 none 0.0000E+00, Nuclide 060:

Pu-239 0.7594336440E+12 0.2390E+03 0.0000E+00 U-235 0.1000E+01 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

I CALCULATION NO. C-1 302-822-E310-082 I REV. No. 0 I PAGENO. D-1 I ATTACHMENT D .RFT File Release Fraction and Timing Name:

Columbia, NUREG-1465 Duration (h): Design Basis Accident O.10OOE-05 O.OQOOE+QO o.OOOOE+00 o.OOOOE+00 Noble Gases:

5.OOO0E-02 0 OOOOE+00 o.OOOOE+00 o .OOOOE+00 Iodine:

2.5000E-04 0 OOOOE+00 o.OOOOE+00 o.OOOOE+00 Cesium:

o.OOOOE+00 o.0000E+00 o.OOOOE+00 o.OOOOE+00 Tellurium:

0o0000E+00 o .OOOE+00 o.OOOOE+00 0 OOOOE+00 Strontium:

o.OOOOE+00 o.0000E+00 o.OOOOE+00 0.OOOOE+00 Barium:

o.OOOOE+00 o.OOOOE+00 O.OOOOE+O0 o.OOOOE+00 Ruthenium:

0.0000E+00 o.OOOOE+00 o.OOOOE+00 o.OOOE+00 Cerium:

o.OOOOE+00 0 OOOOE+00 o.OOOOE+00 o.OOOOE+00 Lanthanum:

o.OOOOE+00 o.OOOOE+00 O.OOOOE+00 o.OOOOE+00 Non-Radioactive Aerosols (kg):

0.0OOOE+00 O.0000E+00 O.0000E+00 0.0000E+00 End of Release File

Enclosure 1 Description and Assessment Page 21 of 22 Attachment 2 Regulatory Guide 1.183 - Conformance Tables

Attachment 2 Description and Assessment Page 1 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 3.1 The inventory of fission products in the reactor core and available Conforms ORIGEN 2 was used to for release to the containment should be based on the maximum full determine core inventory.

power operation of the core with, as a minimum, current licensed Power level used was values for fuel enrichment, fuel burnup, and an assumed core power 1969 MWt to account for equal to the current licensed rated thermal power times the ECCS two% uncertainty (1930 x evaluation uncertainty. The period of irradiation should be of 1.02 = 1969). Fission product sufficient duration to allow the activity of dose-significant inventory is based on an radionuclides to reach equilibrium or to reach maximum values. The average core burnup of core inventory should be determined using an appropriate isotope 1600 effective full power generation and depletion computer code such as ORIGEN 2 or days.

ORIGEN-ARP. Core inventory factors (Ci/MWt) provided in TID 14844 and used in some analysis computer codes were derived for low burnup, low enrichment fuel and should not be used with higher burnup and higher enrichment fuels.

3.1 For the DBA LOCA, all fuel assemblies in the core are assumed to be Conforms For the FHA event not affected and the core average inventory should be used. For DBA involving the entire core, the events that do not involve the entire core, the fission product fission product inventory of inventory of each of the damaged fuel rods is determined by each of the damaged fuel dividing the total core inventory by the number of fuel rods in the rods is determined by core. To account for differences in power level across the core, dividing the total core radial peaking factors from the facility's core operating limits report inventory by the number of (COLR) or technical specifications should be applied in determining fuel rods in the core. This the inventory of the damaged rods. value is further adjusted by the use of the radial peaking factor (1.7).

Attachment 2 Description and Assessment Page 2 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 3.1 No adjustment to the fission product inventory should be made for Conforms For the fuel handling events postulated to occur during power operations at less than full accident, radioactive decay rated power or those postulated to occur at the beginning of core from the time of shutdown is life. For events postulated to occur while the facility is shutdown, modeled. A full power e.g., a fuel handling accident, radioactive decay from the time of fission product inventory is shutdown may be modeled. used.

3.2 The core inventory release fractions, by radionuclide groups, for the Conforms The fractions from Table 1 gap release and early in-vessel damage phases for DBA LOCAs are are used for the previously listed in Table 1 for BWRs and Table 2 for PWRs. These fractions approved LOCA analysis.

are applied to the equilibrium core inventory described in There are no changes being Regulatory Position 3.1. proposed.

Table 1 BWR Core Inventory Fraction Released Into Containment Gap Early Release In-Vessel Group Phase Phase Total Noble Gases 0.05 0.95 1.0 Halogens 0.05 0.25 0.3 Alkali Metals 0.05 0.20 0.25 Tellurium Metals 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals 0.00 0.0025 0.0025 Cerium Group 0.00 0.0005 0.0005 Lanthanides 0.00 0.0002 0.0002

Attachment 2 Description and Assessment Page 3 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 3.2 For non-LOCA events, the fractions of the core inventory assumed Conforms Complies with Note 11 of to be in the gap for the various radionuclides are given in Table 3. Table 3 of the RG.

The release fractions from Table 3 are used in conjunction with the fission product inventory calculated with the maximum core radial peaking factor.

Table 3 Non-LOCA Fraction of Fission Product Inventory in Gap Group Fraction 1-131 0.08 Kr-85 0.10 Other Noble Gases 0.05 Other Halogens 0.05 Alkali Metals 0.12 3.3 Table 4 tabulates the onset and duration of each sequential release Conforms The BWR durations from phase for DBA LOCAs at PWRs and BWRs. The specified onset is Table 4 are used for the the time following the initiation of the accident (i.e., time = 0). The LOCA, modeled in a linear early in-vessel phase immediately follows the gap release phase. fashion as was approved in a The activity released from the core during each release phase previous submittal.

should be modeled as increasing in a linear fashion over the Non-LOCA events are duration of the phase. For non-LOCA DBAs, in which fuel damage is modeled as an instantaneous projected, the release from the fuel gap and the fuel pellet should be release from the fuel to the assumed to occur instantaneously with the onset of the projected water and air space above.

damage.

Table 4 LOCA Release Phases PWRs BWRs Phase Onset Duration Onset Duration Gap Release 0 sec 0.5 hr 2 min 0.5 hr Early In-Vessel 0.5 hr 1.3 hr 0.5 hr 1.5 hr

Attachment 2 Description and Assessment Page 4 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 3.3 For facilities licensed with leak-before-break methodology, the onset Not Applicable Not applicable to the FHA of the gap release phase may be assumed to be 10 minutes. A analysis.

licensee may propose an alternative time for the onset of the gap release phase, based on facility-specific calculations using suitable analysis codes or on an accepted topical report shown to be applicable for the specific facility. In the absence of approved alternatives, the gap release phase onsets in Table 4 should be used.

3.4 Table 5 lists the elements in each radionuclide group that should be Conforms The nuclides used are the considered in design basis analyses. 60 identified as being Table 5 potentially important dose Radionuclide Groups contributors to total effective dose equivalent (TEDE) in the Group Elements RADTRAD code, which Noble Gases Xe, Kr encompasses those listed in Halogens I, Br RG 1.183, Table 5.

Alkali Metals Cs, Rb Tellurium Group Te, Sb, Se, Ba, Sr Noble Metals Ru, Rh, Pd, Mo, Tc, Co Lanthanides La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am Cerium Ce, Pu, Np 3.5 Of the radioiodine released from the reactor coolant system (RCS) to Conforms These chemical forms are the containment in a postulated accident, 95 percent of the iodine assumed in releases from released should be assumed to be cesium iodide (Csl), 4.85 percent fuel pins in the Oyster Creek elemental iodine, and 0.15 percent organic iodide. This includes FHA.

releases from the gap and the fuel pellets. With the exception of elemental and organic iodine and noble gases, fission products should be assumed to be in particulate form. The same chemical form is assumed in releases from fuel pins in FHAs and from releases from the fuel pins through the RCS in DBAs other than

Attachment 2 Description and Assessment Page 5 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments FHAs or LOCAs. However, the transport of these iodine species following release from the fuel may affect these assumed fractions.

The accident-specific appendices to this regulatory guide provide additional details.

3.6 The amount of fuel damage caused by non-LOCA design basis Conforms The fuel damage events should be analyzed to determine, for the case resulting in the assumptions correspond to highest radioactivity release, the fraction of the fuel that reaches or those of the Oyster Creek exceeds the initiation temperature of fuel melt and the fraction of Updated Final Safety fuel elements for which the fuel clad is breached. Although the NRC Analysis Report.

staff has traditionally relied upon the departure from nucleate boiling ratio (DNBR) as a fuel damage criterion, licensees may propose other methods to the NRC staff, such as those based upon enthalpy deposition, for estimating fuel damage for the purpose of establishing radioactivity releases.

4.1.1 The dose calculations should determine the TEDE. TEDE is the sum Conforms TEDE is calculated.

of the committed effective dose equivalent (CEDE) from inhalation Significant progeny included.

and the deep dose equivalent (DDE) from external exposure. The calculation of these two components of the TEDE should consider all radionuclides, including progeny from the decay of parent radionuclides, that are significant with regard to dose consequences and the released radioactivity.

4.1.2 The exposure-to-CEDE factors for inhalation of radioactive material Conforms Federal Guidance Report 11 should be derived from the data provided in ICRP Publication 30, dose conversion factors "Limits for Intakes of Radionuclides by Workers" (Ref. 19). Table 2.1 (DCFs) are used.

of Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion" (Ref. 20), provides tables of conversion factors acceptable to the NRC staff. The factors in the column headed "effective" yield doses corresponding to the CEDE.

Attachment 2 Description and Assessment Page 6 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 4.1.3 For the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , the breathing rate of persons offsite should be Conforms The analysis uses RADTRAD assumed to be 3.5 x 10.4 cubic meters per second. From 8 to 24 default values, which hours following the accident, the breathing rate should be assumed corresponds to the values in to be 1.8 x 10-4 cubic meters per second. After that and until the end Section 4.1.3 of RG 1.183.

of the accident, the rate should be assumed to be 2.3 x 10-4 cubic meters per second.

4.1.4 The DDE should be calculated assuming submergence in semi- Conforms Federal Guidance Report 12 infinite cloud assumptions with appropriate credit for attenuation by conversion factors are used.

body tissue. The DDE is nominally equivalent to the effective dose equivalent (EDE) from external exposure if the whole body is irradiated uniformly. Since this is a reasonable assumption for submergence exposure situations, EDE may be used in lieu of DDE in determining the contribution of external dose to the TEDE. Table 111.1 of Federal Guidance Report 12, "External Exposure to Radionuclides in Air, Water, and Soil" (Ref. 21), provides external EDE conversion factors acceptable to the NRC staff. The factors in the column headed "effective" yield doses corresponding to the EDE.

4.1.5 The TEDE should be determined for the most limiting person at the Conforms EAB. The maximum EAB TEDE for any two-hour period following the start of the radioactivity release should be determined and used in determining compliance with the dose criteria in 10 CFR 50.67.

The maximum two-hour TEDE should be determined by calculating the postulated dose for a series of small time increments and performing a "sliding" sum over the increments for successive two-hour periods. The maximum TEDE obtained is submitted. The time increments should appropriately reflect the progression of the accident to capture the peak dose interval between the start of the event and the end of radioactivity release (see also Table 6).

Attachment 2 Description and Assessment Page 7 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 4.1.6 TEDE should be determined for the most limiting receptor at the Conforms outer boundary of the low population zone (LPZ) and should be used in determining compliance with the dose criteria in 10 CFR 50.67.

4.1.7 No correction should be made for depletion of the effluent plume by Conforms No such corrections are deposition on the ground. made for the FHA analysis.

4.2.1 The TEDE analysis should consider all sources of radiation that will Conforms The principal source of dose cause exposure to control room personnel. The applicable sources within the control room from will vary from facility to facility, but typically will include: the FHA is due to airborne radioactivity drawn into the

Contamination of the control room atmosphere by the intake or control room (unfiltered).

infiltration of the radioactive material contained in the radioactive plume released from the facility,

Contamination of the control room atmosphere by the intake or infiltration of airborne radioactive material from areas and structures adjacent to the control room envelope,

Radiation shine from the external radioactive plume released from the facility,

" Radiation shine from radioactive material in the reactor containment,

" Radiation shine from radioactive material in systems and components inside or external to the control room envelope, e.g., radioactive material buildup in recirculation filters.

The radioactive material releases and radiation levels used in the Conforms The source term, transport, control room dose analysis should be determined using the same and release methodology is source term, transport, and release assumptions used for the same for both the control determining the EAB and the LPZ TEDE values, unless these room and offsite locations.

assumptions would result in non-conservative results for the control room.

Attachment 2 Description and Assessment Page 8 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments 4.2.3 The models used to transport radioactive material into and through Conforms The RADTRAD model for the the control room, and the shielding models used to determine FHA analysis is structured to radiation dose rates from external sources, should be structured to provide suitably conservative provide suitably conservative estimates of the exposure to control estimates of the exposure to room personnel. control room personnel.

4.2.4 Credit for engineered safety features that mitigate airborne Conforms Control room pressurization radioactive material within the control room may be assumed. Such and intake filtration are not features may include control room isolation or pressurization, or credited in the Oyster Creek intake or recirculation filtration. Refer to Section 6.5.1, "ESF FHA analysis.

Atmospheric Cleanup System," of the SRP (Ref. 3) and Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Post-accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" (Ref. 25), for guidance.

4.2.5 Credit should generally not be taken for the use of personal Conforms Such credits are not taken.

protective equipment or prophylactic drugs. Deviations may be considered on a case-by-case basis.

4.2.6 The dose receptor for these analyses is the hypothetical maximum Conforms Based on RADTRAD default exposed individual who is present in the control room for 100% of values, which corresponds to the time during the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the event, 60% of the time the values in Section 4.2.6 of between 1 and 4 days, and 40% of the time from 4 days to 30 days. RG 1.183.

For the duration of the event, the breathing rate of this individual should be assumed to be 3.5 x 10-4 cubic meters per second.

4.2.7 Control room doses should be calculated using dose conversion Conforms The equation given is utilized factors identified in Regulatory Position 4.1 above for use in offsite for finite cloud correction dose analyses. The DDE from photons may be corrected for the when calculating external difference between finite cloud geometry in the control room and the doses due to the airborne semi-infinite cloud assumption used in calculating the dose activity inside the control conversion factors. The following expression may be used to room.

correct the semi-infinite cloud dose, DDE-, to a finite cloud dose,

Attachment 2 Description and Assessment Page 9 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments DDEfinite, where the control room is modeled as a hemisphere that has a volume, V, in cubic feet, equivalent to that of the control room (Ref. 22).

08 DDEfinite = DDEO.V 1173 4.3 The guidance provided in Regulatory Positions 4.1 and 4.2 should Conforms A qualitative assessment of be used, as applicable, in re-assessing the radiological analyses the regulatory positions on identified in Regulatory Position 1.3.1, such as those in NUREG-0737 source term indicate that (Ref. 2). Design envelope source terms provided in NUREG-0737 with no new operator actions should be updated for consistency with the AST. In general, required in areas such as radiation exposures to plant personnel identified in Regulatory ECCS pump rooms, doses Position 1.3.1 should be expressed in terms of TEDE. Integrated would be lower than radiation exposure of plant equipment should be determined using currently reported.

the guidance of Appendix I of this guide.

5.1.1 The evaluations required by 10 CFR 50.67 are re-analyses of the Conforms The FHA analysis has been design basis safety analyses and evaluations required by 10 CFR prepared, reviewed, and is 50.34; they are considered to be a significant input to the maintained in accordance evaluations required by 10 CFR 50.92 or 10 CFR 50.59. These with quality assurance analyses should be prepared, reviewed, and maintained in programs that comply with accordance with quality assurance programs that comply with Appendix B, "Quality Appendix B, "Quality Assurance Criteria for Nuclear Power Plants Assurance Criteria for and Fuel Reprocessing Plants," to 10 CFR Part 50. Nuclear Power Plants and Fuel Reprocessing Plants,"

to 10 CFR Part 50.

5.1.2 Credit may be taken for accident mitigation features that are Conforms The analysis takes no credit classified as safety-related, are required to be operable by technical for safety-related features.

specifications, are powered by emergency power sources, and are either automatically actuated or, in limited cases, have actuation requirements explicitly addressed in emergency operating procedures. The single active component failure that results in the

Attachment 2 Description and Assessment Page 10 of 14 Table 1: Conformance with Regulatory Guide (RG) 1.183 Main Sections RG Oyster Creek Section RG Position Analysis Comments most limiting radiological consequences should be assumed.

Assumptions regarding the occurrence and timing of a loss of offsite power should be selected with the objective of maximizing the postulated radiological consequences.

5.1.3 The numeric values that are chosen as inputs to the analyses Conforms Conservative values are used required by 10 CFR 50.67 should be selected with the objective of throughout the FHA analysis.

determining a conservative postulated dose. In some instances, a particular parameter may be conservative in one portion of an analysis but be nonconservative in another portion of the same analysis.

5.1.4 Licensees should ensure that analysis assumptions and methods Conforms Analysis assumptions and are compatible with the AST and the TEDE criteria, methods are compatible with the AST and the TEDE criteria.

5.3 Atmospheric dispersion values (X/Q) for the EAB, the LPZ, and the Conforms ARCON96 was used to control room that were approved by the staff during initial facility determine control room licensing or in subsequent licensing proceedings may be used in atmospheric dispersion performing the radiological analyses identified by this guide. values for ground level releases and for reactor Methodologies that have been used for determining X/Q values are building stack releases documented in Regulatory Guides 1.3 and 1.4, Regulatory Guide (analysis only uses ground 1.145, "Atmospheric Dispersion Models for Potential Accident level release value).

Consequence Assessments at Nuclear Power Plants," and the RG 1.145 methodology was paper, "Nuclear Power Plant Control Room Ventilation System used to determine EAB and Design for Meeting General Criterion 19" (Refs. 6, 7, 22, and 28). LPZ atmospheric dispersion The methodology of the NRC computer code ARCON96 (Ref 26) is values and control room generally acceptable to the NRC staff for use in determining control atmospheric dispersion room X/Q values. values for elevated releases.

Attachment 2 Description and Assessment Page 11 of 14 Table 2: Conformance with RG 1.183 Appendix B (Fuel Handling Accident)

RG Oyster Creek Section RG Position Analysis Comments Acceptable assumptions regarding core inventory and the release of Conforms The same core inventory radionuclides from the fuel are provided in Regulatory Position 3 of used in the LOCA analysis, this guide. previously approved by the NRC, is used for the FHA analysis.

1.1 The number of fuel rods damaged during the accident should be Conforms based on a conservative analysis that considers the most limiting case. This analysis should consider parameters such as the weight of the dropped heavy load or the weight of a dropped fuel assembly (plus any attached handling grapples), the height of the drop, and the compression, torsion, and shear stresses on the irradiated fuel rods. Damage to adjacent fuel assemblies, if applicable (e.g., events over the reactor vessel), should be considered.

1.2 The fission product release from the breached fuel is based on Conforms Regulatory Position 3.2 of this guide and the estimate of the number of fuel rods breached. All the gap activity in the damaged rods is assumed to be instantaneously released. Radionuclides that should be considered include xenons, kryptons, halogens, cesiums, and rubidiums.

1.3 The chemical form of radioiodine released from the fuel to the spent Conforms All iodine added to pool is fuel pool should be assumed to be 95% cesium iodide (Csl), 4.85 assumed to dissociate.

percent elemental iodine, and 0.15 percent organic iodide. The Csl released from the fuel is assumed to completely dissociate in the pool water. Because of the-low pH of the pool water, the iodine re-evolves as elemental iodine. This is assumed to occur instantaneously. The NRC staff will consider, on a case-by-case basis, justifiable mechanistic treatment of the iodine release from the pool. I

Attachment 2 Description and Assessment Page 12 of 14 Table 2: Conformance with RG 1.183 Appendix B (Fuel Handling Accident)

RG Oyster Creek Section RG Position Analysis Comments 2 If the depth of water above the damaged fuel is 23 feet or greater, the Conforms A water depth of 23 feet is decontamination factors for the elemental and organic species are analyzed with an overall DF 500 and 1, respectively, giving an overall effective decontamination of 200 for the most limiting factor of 200 (i.e., 99.5% of the total iodine released from the case of a drop in the reactor damaged rods is retained by the water). This difference in vessel.

decontamination factors for elemental (99.85%) and organic iodine (0.15%) species results in the iodine above the water being composed of 57% elemental and 43% organic species. If the depth of water is not 23 feet, the decontamination factor will have to be determined on a case-by-case method (Ref. B-i).

3 The retention of noble gases in the water in the fuel pool or reactor Conforms cavity is negligible (i.e., decontamination factor of 1). Particulate radionuclides are assumed to be retained by the water in the fuel pool or reactor cavity (i.e., infinite decontamination factor).

4.1 The radioactive material that escapes from the fuel pool to the fuel Conforms building is assumed to be released to the environment over a 2-hour time period.

4.2 A reduction in the amount of radioactive material released from the Not Applicable No credit is taken for fuel pool by engineered safety feature (ESF) filter systems may be filtration from the reactor taken into account provided these systems meet the guidance of building.

Regulatory Guide 1.52 and Generic Letter 99-02 (Refs. B-2, B-3).

Delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system (21) should be determined and accounted for in the radioactivity release analyses.

4.3 The radioactivity release from the fuel pool should be assumed to be Not Applicable Two-hour release to the drawn into the ESF filtration system without mixing or dilution in the environment is assumed.

fuel building. If mixing can be demonstrated, credit for mixing and dilution may be considered on a case-by-case basis. This evaluation should consider the magnitude of the building volume and exhaust

.Attachment 2 Description and Assessment Page 13 of 14 Table 2: Conformance with RG 1.183 Appendix B (Fuel Handling Accident)

RG Oyster Creek Section RG Position Analysis Comments rate, the potential for bypass to the environment, the location of exhaust plenums relative to the surface of the pool, recirculation ventilation systems, and internal walls and floors that impede stream flow between the surface of'the pool and the exhaust plenums..

5.1 If the containment is isolated during fuel handling operations, no Not Applicable Containment is not isolated.

radiological consequences need to be analyzed.

5.2 If the containment is open during fuel handling operations, but Not Applicable Containment is not isolated.

designed to automatically isolate in the event of a fuel handling accident, the release duration should be based on delays in radiation detection and completion of containment isolation. If it can be shown that containment isolation occurs before radioactivity is released to the environment, no radiological consequences need to be analyzed.

5.3 If the containment is open during fuel handling operations (e.g., Conforms The radioactive material that personnel air lock or equipment hatch is open), the radioactive escapes from the reactor material that escapes from the reactor cavity pool to the cavity pool is released to containment is released to the environment over a 2-hour time the environment over a 2-

_____period. hour time period.

5.4 A reduction in the amount of radioactive material released from the Not Applicable No credit is being taken for containment by ESF filter systems may be taken into account filtration of release from the provided that these systems meet the guidance of Regulatory Guide reactor building.

1.'52 and Generic Letter 99-02 (Refs. B-2 and B-3). Delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system should be determined and accounted for in the radioactivity release analyses.

5.5 Credit for dilution or mixing of the activity released from the reactor Not Applicable No credit is taken for cavity by natural or forced convection inside the containment may dilution or mixing of the be considered on a case-by-case basis. Such credit is generally activity released from the limited to 50% of the containment free volume. This evaluation reactor cavity.

Attachment 2 Description and Assessment Page 14 of 14 Table 2: Conformance with RG 1.183 Appendix B (Fuel Handling Accident)

RG Oyster Creek Section RG Position Analysis Comments should consider the magnitude of the containment volume and exhaust rate, the potential for bypass to the environment, the location of exhaust plenums relative to the surface of the reactor cavity, recirculation ventilation systems, and internal walls and floors that impede stream flow between the surface of the reactor cavity and the exhaust plenums.

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