Text

Calculation for Alternative Source Term, H21C096, Ul CRDA, AST Methodology
	ML070110305
Person / Time
Site:	Nine Mile Point
Issue date:	12/15/2006
From:	Metcalf J, Pustulka H; Nine Mile Point
To:	; Office of Nuclear Reactor Regulation
References
	H21C096
	Download: ML070110305 (80)
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Nine Mile Point Unit 1 Alternative Source Term Calculation H21C096 "IUl CRDA, AST Methodology"

Engineering CALCULATONTCOVERSHEET79 Services ~Last Attachment 2 Project: NINE MILE POINT NUCLEAR STATION Unit (1,2 or O=Both): Discipline: CR Title Calculation No. H21C096 U1 CRDA, AST Methodology (Sub)system(s) Building Floor Elev. Index No, N/A IN/A N/A IN/A Originator(s) H. Pusrulka (Design Input Compilation, Case I and Appendices A, B, C & E)/ J. Metcalf (Case 2 and Appendix C & D).

Reviewer(s)/Approver(s) MI. Berg NMP Acceptance: IZ/45/svo Eal., CR, or Rev Description Change No. Prepared By Date Reviewed by Date App Date Wi ataced 12130 00 Iiia eeaeW4See attached Sig, Sheet 112/12/06 Sheeatace 12/13/06 ______ __

iInia ReleaseShet

-~ 4 + + 4 4 4

-~ 4 .4- 4- 4. 4 4.-

Computer Output/Microfilm separately filed? (Yes/No/N/A) -No- Safety Class: (*SRINSRJQxx): SR

IfSR, attach or reference the associated Design Verification Report.

Superseded Document(s):

Document Cross Reference(s) - For additional references see page(s) 7..Output provided? Y If yes, group(s) j~~

(Y/N) L&/

Ref Ref No. Document No, Type Index Sheet Rev No. Document No. Type Index Sheet Rev General

References:

Remarks: s 4L 4 NT(Uce4r-k wJ Confirmation Required (Yes7o): N' b Final Issue Status ITurnover See Page(s): PReq'd (Yes/N/A): '4'!

10 cFR5D.59 Evaluation Number(s): Component ID(s)(As shown inMEIL): 13 1A, I

Copy of Applicability Determination or 50.59 Screen Attached? Yeso No*ED N/A K *If"No", location of AD/Screen?

Key Words: Control Rod Drop Accident, cRDA, Design Basis, Dose, Accident

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[Originator/Date Project:- Nine Mile Point Nuclear Station Case 1:1-H.

Design Input Comnpilation Pustulka 12/12/06, Case_2: J.Metcalf 12/12/06 Reiewer/Date M. erg 12/13/06 Unit: -1 Calculation No.

H21 C096 Disposition: -W Revision 0

List of Effective Pages Page Latest Page Latest Page Latest Page Latest Page Latest Page Latest No. Rev. No. Rev, No. Rev. No. Rev. No. Rev. No. Rev.

1 0 Al -A5 0 1la 0 Bl-B2 0 2 0 01-04 0 3 0 01-039 0 4 0 El-Eli1 0 5 0 Attachi1 0 6 0 Attach 2 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 Total Number of Calculation Pages _ 79

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page 3-(Next -4 Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: a/Kq Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: H.Pustulka 12/12/06, M. Berg 12/13/06 H21 0096 0 Case 2: J.Metcalf 12/12/06 Table of Contents CALCULATION COVER SHEET ............................................................................... 1 List of Effective Pages ..............................................-...--.......... .... .........- _2 Table of Contents ............................................................................................... 3 Purpose.................................. ....................................................................... 4 Summary of Results ............................................................................................ 5 Methodology ........................................ I.......................................I...... ...... I.........5 Assumptions .................................................................................................... 6 References...................................................................................................... 7 Design Inputs ................................................................................................... 8 Calculation ..................................................................................................... 11 Case 1 ......................................................................................................... 11 Case 2-............................. ............................................................................ 13 Conclusions.................................................................................................... 15 Appendix A: Spreadsheet for the Calculation of Offsite and Control Room Doses (5Pages)

Appendix B: Calculation of the Reference Activity Release for the Main Steam Line Radiation Monitor Gamma Dose Calculation (2 Pages)

Appendix C: Steam Line Radiation Monitor Response (4Pages)

Appendix D: RADTRAD CRIDA Dose Analysis for Case 2 (39 Pages)

Appendix D-1: Primary Input (.psf) file, Plant Scenario File, NMP1 CRDA.psf ............................ D3 Appendix D-2: Secondary Input (.nif, .rft, .inp) files Appendix D-2.1: Nuclide Information File, nmp.nif............................................. D9 Appendix D-2.2: Release Fraction File, NMP1-crda rft ............................D22 Appendix D-2.3: Dose Conversion Factor File, loo6fgrnmpl .inp .............................. D23 Appendix D-3: RADTRAD Output (.o0) file, NMP1CRDA.oO (Excerpt) ................................. D38 Appendix E: Check Calculation using STAP.DOSE for CRDA Dose Analysis, Case 2 (11 Pages)

Attachment E-1: STARDOSE Library File (LIBFILE1 .txt) ....................................... E3 Attachment E-2: STARDOSE Main Input File for Case 2....................................... E6 Attachment E-3: STARDOSE Results for Case 2 (Excerpts) .................................. Eli Attachment 1: Design Verification Report (1Page)

Attachment 2: Design Verification Checklist (1Page)

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -4 (Next -5 Project.' Nine Mile Point Nuclear Station Unit: _1_ Disposition.- 01A Originator/Date Design Input Compilatio an eiwer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. erg 12/13/06 H21 C096 0 Case 2: J.Metcalf 12/12/06 Purpose This calculation is prepared by Polestar Applied Technology, Inc. at the request of Nine Mile Point Nuclear Station, a subsidiary of Constellation Energy Group (NMP) to determine the offsite and control room doses following a Control Rod Drop Accident (CRDA). The analysis includes releases through two separate pathways (or cases) and evaluates the radiological impact at the Exclusion Area Boundary (EAB), Low Population Zone (LPZ) and control room (CR). The cases are as follows:

o Case 1: Leakage from the main condenser based on the assumption of manual isolation of the Main Steam Isolation Valves (MSIIVs) o Case 2: Main Condenser not isolated, mechanical vacuum pump in operation.

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[Originator/Date Project: Nine Mile Point Nuclear Station Design Input Compilation and Case 1:H.Pustulka 12/12/06, Case 2: J.Metcalf 12/12/06 Reviewer/Date Unit:

M. Berg 12/13/06 1I Calculation No.

H21 C096 Disposition: #u/A, Revision 0

Summary of Results Table 1: CRDA TEDE Doses by Location Case 1 Case 2 Regulatory Limit

___(rem) (rem) (rem)

EAB 6.29E-01 0.342 6.3 LPZ 5.39E-02 0.211 6.3 CR 6.12E-0 1 1.61 5.0

1. The most limiting person at the EAB would not be subjected to radiation exposure resulting in doses in excess of 6.3 rem TEDE over 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

2. The most limiting person at the inner boundary of the LPZ would not be subjected to radiation exposure resulting in doses *inexcess of 6.3 rem TEDE over 30 days, and finally,

3. The hypothetical maximum exposed control room operator would not be subjected to radiation exposure resulting in doses in excess of 5 rem over 30 days.

Note that for the EAB dose, the worst two hours is from t =1.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to t =3.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . This is the time of peak activity in the main condenser.

This table shows that all cases meet the applicable limits at all locations.

Methodology The main steam line radiation monitors need to be sufficiently sensitive to trip the mechanical vacuum pump in the event of gross fuel failures. Of particular interest is the response to a CRDA.

The NRC requires an analysis of the CRDA in which it is assumed that the released activity from the damaged fuel is instantaneously transported to the main condenser, and the associated activity concentration will certainly exceed the main steam line radiation monitor safety limit. For this analysis (Case 1), it is assumed that the steam lines provide a DF of 10 for iodine and a DF of 100 for other solids, as does the main condenser. It is also assumed that the release from the main condenser (one percent per day) stops at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the start of the accident.

In the instance where the transport of activity is much slower, as in Case 2, the main steam line radiation monitors may not have their safety limit exceeded. Under these conditions, the main condenser may not isolate (i.e., the mechanical vacuum pump could be operating and continue

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -6 (Next -7 Project: Nine Mile Point Nuclear Station Unit: 1- Disposition: Plik Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21 C096 0 Case 2:J.Metcalf 12/12/06 operating). This case is analyzed in the following way:

I. Establish a "base" steam line activity concentration (G/m 3) with the radionuclide mnix corresponding to the CRDA analysis ftrom Case 1.

2. Calculate the dose rate at the steam line radiation monitor for the base steam line activity concentration.

3. Using the known threshold dose rate corresponding to the safety limrit for the main steam line radiation monitor, ratio that dose rate to the dose rate calculated from the known concentration to determine the concentration that would produce the safety limit dose rate.

4. Create a source volume of a size that would contain all of the CRDA activity at the threshold concentration for detection.

5. Define the maximum volumetric steam flow with the mechanical vacuum pump in operation.

6. Perform a dose analysis using RADTRAD [Ref 2] with a check using STARDOSE [Ref 3]

using a model like that of Case I except with a time-dependent flow into the main condenser based on the maximum volumetric steam flow with the mechanical vacuum pump in operation, the mechanical vacuum pump flow out of the main condenser, and stack XIQs (corresponding to the mechanical vacuum pump flowpath). Assume the same DFs and end of release from the main condenser (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) as Case 1.

7. Compare the TEDE values obtained in Step 6 (using DCFs consistent with References 5 and 6) with the 6.3 rem BWR CRDA TEDE limit for offsite doses and the 5 rem TEDE limit for the control room [Ref 1].

The dose analysis was conducted in full compliance with NRC Regulatory Guide 1.18 3 [Ref 1]. This calculation determines the offsite and control room doses due to a CRDA. Due to the simplicity of Case 1, the spreadsheet methodology outlined in Appendix A was used. Case 2 required the use computer code RADTRAD 3.03 [Ref 2] to determine the activity releases, offsite dose and control room dose.

Verification of the RADTRAD runs was performed using the STAiRDOSE 1.01 computer code [Ref 3]

and is documented in Appendix F.

Assumptions Assumption 1: The Case 1 release is from the main condenser via the Reactor Building and at ground level. Case 2 releases are from the plant stack.

Justification: The exact leak location for the assumed 1% per day condenser leakage is not known, but it is conservatively assumed to be at ground level. The mechanical vacuum pump releases well be via the plant stack (offgas release path).

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Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition: 01 Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H210C096 0 Case 2: J.Metcalf 12/12/06 Assumption 2: For Case 2, attenuation of the environmental release by the offgas system is not credited. However, the stack release is credited.

Justification: Credit for the offgas system is permitted in Reference 1; it Is conservative to ignore this credit. The credit is being taken only to the extent that the stack is assumed to be the release point.

Assumption 3: Assume an infinite control room exchange rate with the environment for Case 2.

Justification: Using 1E6 cfm of control room supply air as unfiltered makeup ensures that control room operator dose is based on the same assumption of infinite exchange with the environment as Case 1.

References

1. "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", US NRC Regulatory Guide 1.183, Revision 0, July 2000.

2. S. L. Humphries et al, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", NUIREG/CR-6604, Sandia National Laboratories, December 1997.

3. For calculation verification purposes only: "STARDOSE Model Report, Polestar Applied Technology, Inc., PSAT C109.03 January 1997.

4. PSAT 4026CF.QA.03, "Design Database for Application of the Revised DBA Source Term to Nine Mile Point", Revision 0

5. Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," EPA 520/1-88-020, U.S. Environmental Protection Agency, Washington, DC, 1988.

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

EPA-402-R-93-08 1, U.S. Environmental Protection Agency, Washington, DC, 1993.ý

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(Next -9 Project:-Nine Mile Point Nuclear Station Unit: -1 Disposition: t.3/Ax IOriginator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21 C096 0 Case 2: J.Metcalf 12/12/06 Ref.

Design Inputs Design Input Data (Reference 4 for all inputs, Item numbers given in brackets):

Power level = 1887 MWt [1. 1]

Core inventories [1.2]

Nuclide : CiIMWt NuldLC/~ Nuclide CI~

Kr83m 3.27E+03 RuOM 1.76E+04 0s134 7.29E+03 Kr85 3.93E+02 RhlO5 2.84E+04 Csl36 2.28E+03 Kr85m 6.82E+03 Sb127 3.01 E+03 Cs137 4.35E+03 Kr87 1.30E+04 Sb129 8.91 E+03 Ba137m 4.12E+03 Kr-88 1.83E+04 Te127 3.OOE+03 Ba1 39 4.89+04 Kr89 2.22E+04 Te127m 4.05E+02 Bal40 4.71 +04 Rb86 7.29E+01 Tel129 8.76E+03 La140 5.12+04 Sr89 2.45E+04 Te129m 1.30E+03 La141 4.45+04 Sr9O 3.14E+03 Tel31m 3.97E+03 La142 4.29+04 Sr9l 3.10E+04 Te132 3.85E+04 Cel4l 4.47+04 Sr92 3.38E+04 1131 2.71 E+04 0e143 4.11+04 Y90 3.24E+03 1132 3.92E+04 Ce144 3.70+04 Y91 3.18E+04 1133 5.51 E+04 Pr-143 3.97+04 Y92 3.40E+04 1134 6.03E+04 NdJ147 1.80+04 Y93 3.96E+04 1135 5.16E+04 Np239 5.78E+05 Zr95 4.46E+04 Xe131m 3.04E+02 Pu238 1.45E+02 Zr97 4.51 E+04 Xe133 5.27E+04 Pu239 1.34E+01 Nb95 4.48 E+04 Xel 33m 1.63E+03 Pu240 1,89E+01 M099 5.13 E+04 Xe135 1.91 E+04 Pu241 5.49E+03 Tc99m 4.49 E+04 Xel35m 1.09E+04 Am241 7.48E+00 RulO3 4.29 E+04 Xe1 37 4.80E+04 0m242 1.85E+03 RuOM 3.01 E+04 Xe138 4.50E+04 m24 1.23E+02 Peaking factor = 1.8 [1.6]

Total number of fuel assemblies in core 532

=53 [1.5]

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Project:- Nine, Mile Point Nuclear Station Unit: -1 Disposition: .~

Originator/Date Design Input Compilation and FReviewer/Date -Calculation No. Revision Case 1:H.Pustulka 12/12/06,M.Br 123/6H1C90 Case 2: J. Metcalf 12/12/06M.Br123/6H1C90 Ref.

Fuel failure: 850 pins (conservatively based on 8x8 fuel) for a failure fraction of 0.0258 [2.12]

No pins are assumed to melt [2.13]

Release fractions for all radionuclide groups [2.14]

Radio- Release Fraction Release Fraction Fraction of Fraction of Condenser nuclide from Gap to from Melted Fuel Release That Activity Available for Group Coolant to Coolant Reaches the Release to Condenser Environment Noble Gas 10% 100% 100% 100%

Iodine 10% 50% 10% 10%

Br 5% 30% 1% 1%

Cs, Rb 12% 25% 1% 1%

Te Group 0% 5% 1% 1%

Ba,Sr 0% 2% 1% 1%

Noble Mtls 0% 0.25% 1% 1%

Ce Group 0% 0.05% 1% 1%

La Group 0% 0.02% 1% 1%

Leakage rate from main condenser to environment, Case 1 = 1%per day [3.161 Control Room volume = 1.35E+05 cuft [3.9]

Control Room intake (unfiltered): 1E+06 cfmn (Assumption 3)

XIQ values in sec/m3:

Building Releases Worst 2 0-8 hr 8-24 hr 1-4 day 4-30 day

.hour*

EAB ground [5.1] 1.9E-04 N/A N/A N/A N/A EAB stack[ 5.1] 5.98E-05 N/A N/A N/A N/A LPZ ground[ 5.21 1.63E-05 1.63E-05 l.1OE-05 4.67E-06 1.37E-06 LPZ stack[ 5.2] 2.12E-05 ,1.26E-06 8.40E-07 3.45E-07 1.11E-07 Control Room ground (RB)[ 5.3] 4.82E-04 2.6 1E-04 9.25E-05 6.70E-05 4.93E-05 Control Room ground (TB)[ 5.3] 1.03E-03 5.85E-04 2.07E-04 1.75E-04 1.52E-04 Control Room stack[ 5.31 2.27E-04 1.26E-04 4.30E-05 3.58E-05 2.59E-05

For the LPZ, value is based on the worst 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Control Room breathing rates in m3/s [ 5.41 0-30 days 3.5E-4

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page (Next .

Project: Nine Mile Point Nuclear Station Un-it: 1 Dispositio~n: Ji/x Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision ICase 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21C0096 0 Case 2: J.Metcalf 12/12/06 Ref.

EAR & LPZ breathing rates in m3/s [5.4]

0-8 hr 3.5E-4 1-4 days 1.8E-4 4-30 days 2.3E-4 Control Room occupancy factors [5.5]

0 -24 hours 1.0 1-4 days 0.6 4-30 days 0.4 The main condenser mechanical vacuum pump volumetric flowrate: 2000 cfm [3.14]

Main condenser volume: 50,000 ft3 [3.15]

Main steam line radiation monitors "see" at least approximately one steam line diameter of the steam line on each side of the detector point. One detector is located 2'0" south of column line J and one 2'8" south of column line J with the steam line turning to run north horizontally 47'" south of column line J. The reactor building wall is 1'5" north of column line J. For a steam line OD of 24', this means that the detector 2'8" south of colunrm line J can see the horizontal steam line run approximately 0.95 diameters south and 2.05 diameters north, and the detector at 2'0" south of column line J can see the horizontal run approximately 1.68 diameters south and 1.32 diameters north. The former arrangement will produce a lower identified dose and is therefore limniting. [7.12]

Main steam lines are 8'0" center-to-center at the radiation monitor location [7.12]

Radiation monitors are located just below the steam line centerline 0.46 feet based on the centerline of the steam lines being at elevation 264'1/2" and the monitors being at 2637'7 [7.12]

In plan view, the detectors are located two feet from the steam line centerline (two feet on either side of column line 8 (Distance from the detector to the steam line centerline considering both the vertical and horizontal offset is, therefore, 2.05 feet.) [7.12]

The steam line wall thickness is: 1.22" [7.12]

(OD =24" and lID = 21.56")

Maximum safety limit for the MSL radiation monitors is 5 x background (The background is 600 mR/hr [Item 7.13]. Therefore, the maximum safety lirmit is 3000 mR/hr.

Operators will be alerted to high radiation in the steam lines at this level and the mechanical vacuum pump will trip.)

Maximum steam flow for mechanical vacuum pump operation: 2.8E5 Ibm/hr [7.2]

Minimum reactor pressure for mechanical vacuum pump operation: 300 psia[7] [7.3]

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page - 11 (Next Project. Nine Mile Point Nuclear Station Unit: 1 Disposition: L)/j Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21 C096 0 Case 2: J.Metcalf 12/12/06 r~ef.

Calculation Case I Released activity from the damaged fuel is instantaneously transported to the main condenser and the associated activity concentration is assumed to exceed the main steam line radiation monitor safety limit and the main condenser isolates. Release to the environment is due to condenser leakage.

100% of the noble gases released from the damaged fuel rods into the reactor vessel, 10% of the iodines, and 1%of cesiums/rubidiums are assumed to reach the reactor building and condenser.

The flow from the condenser to the environment consists of 1%leakage/day for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The condenser release is assumed to be direct to the environment. 100% of the noble gases released to the condenser, 10% of the iodines, and 1%of cesiums/rubidiums are assumed to reach the environment.

Case I is analyzed using a spreadsheet methodology as discussed in Appendix A. The spreadsheet inputs are described below.

Scaling Factors (Rows 4, 5 & 6):

Scaling Factor 1 is the Power Level in MW(t), used to convert the core inventory concentration to total activity. Scaling Factor 2 is the peaking factor. Scaling Factor 3 is the gap fraction, multiplied by the failure fraction multiplied by the 1%per day release.

DF (Row 7)

DE for Elemental I and Alkali metals is determined taking the inverse of the product of the fraction of release that reaches the condenser and the fraction of condenser activity available for release to the environment. For Elemental I: l/(10%*10%)=1OO. DF for Alkali Metals 1/(1%*1%)=10000.

Source in Ci/MW(t) (column 2):

Items are taken from the core inventories presented in Item 1.2 of Reference 4.

Nuclide Specific Scaling Factor (colum-n 3):

The group specific release fraction from the gap to the coolant is used to scale the nuclides accordingly.

A gap release fraction of 10% has already been taken into account in scaling factor 3, therefore nuclide groups with a release fraction of 10% use a scaling factor of 1. Iodine is partitioned such that 3% of the total released to the environment is organic iodine, and the balance is elemental iodine. Recognizing that the elemental iodine is treated with a DF of 100, the scaling factor for organic iodine is I1*(I/l100)*3 % or 0.0003. Elemental iodine conservatively uses a scaling factor of 1. Cs and Rb use a scaling factor 12%/1 0%=l .2 The results of this calculation can be seen in Table 2 below.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page (Next Project:- Nine Mile Point Nuclear Station Unit. -1 Disposition- W~A~

Originator/Date Design Input Compilation and FReviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21C0096 0 Case 2: J.Metcalf 12/12/06 Ref.

Table 2: CRDA Case 1 Dose Analysis Results N-MP I CRDA EAB LPZ CR Dispersion (XIQs) 1.90E-04 1.63E-05 1.03E-03 sec/m3 CR Vol= 135000 ft3 w/ finite volume gamma correction = 0.0462 12 Scaling Factor 1 = 1887 MW(t)

Scaling Factor 2 = 1.8 Peaking Factor Scaling Factor 3= 2.60E-05 (0. 1 gap x 0.026 core x 0.0 1 release)

DF for Elemental I 100 DF for Alkali Metals: 1.0OE+04 r 7 V I r r Nuclide- WB CEDE TEDE CR EA-B LPZ CR Source: Specific DCF DCF DCF DCF TEDE TEDE TEDE Units>>> Ci/MW(t) Scaling rem-m3 rem/Ci rem-m3 rem-m3 rem rem rem Nuclide Factor Ci-sec Ci-sec C i-sec Kr83m I3.27E+03 5.5 5E-06 0 5.55E-06 2.56E-07 3.05E-07 2.61E-08 7.63E-08 Kr85m 6.82E+03) 0.0277 0 0.0277 0.00 128 3.17E-03 2.72E-04 7.94E-04 Kr85 3.93 E+i02 0.00044 0 0.00044 2.03E-05 2.90E-06 2.49E-07 7.27E-07 1Q87 1.30E+04 0.152 0 0.152 0.007024 3.32E-02 2.84E-03 8.3) IE-03 Kr88 1.83E+04 0.50 1 8.36E+/-01 0.53026 0.0524 12 1,63E-01 1.40E-02 8.72E-02 1Q89 2.22E+04 0.323 0 0.323 0.0 14926 1.20E-01 1.03E-02 3.0 1E-02 Xel3lm 3.04E+02 0.00144 0 0.00144 6.65E-05 7.35E-06 6.30E-07 1.84E-06 XelI33m 1.63 E-t03 0.00507 0 0.00507 0.000234 1.39E-04 1.19E-05 3.47E-05 Xe 133 5,27E+04 0.00577 0 0.00577 0.000267 5.1OE-03 4.3 8E-04 1.28E-03 Xel 35m 1.09E+04 0.0755 0 0.0755 0.003489 1.38E-02 1.1 SE-03 3.46E-03 Xe135 1.91lE+i04 0.044 0 0.044 0.002033 1.41E-02 1.2 tE-03 3.53E-03 Xe137 4.80E+04 0.0303 0 0.0303 0.0014 2.44E-02 2.09E-03 6.11 E-03 Xe 138 4.50E+04 I 0.2 13 0 0.213 0.009843 1.61E-01 1.38E-02 4.03E-02 1131 Org 2.7 1E+04 0.0673) 3.29E+04 11.5823 11.5 1811 1.58E-03 1.36E-04 8.52E-03 11320rg 3 .92E+04 0.4 14 3.8 1E+/-02 0.54735 0. 152482 1.08E-04 9.27E-06 1.63E-04 11330rg 5.5 1lE+04 1. 0.109 5.85E+/-03 2. 1565 2.052537 5.98E-04 5.13E-05 3.09E-03) 11340rg 6.03E+'04 0.481 1.3 1E+02 5.27E-01 0.068078 1.60E-04 1.37E-05 1.12E-04 11350rg 5.16E+04 0.307 1.23E+03) 0.7375 0.444687 1.92E-04 1.64E-05 6.26E-04 1.

113 lElem 2.7 1E+04 0.0673 3 .29E+04 11.5823 11.5 1811 5.27E-02 4.52E-03 2.84E-0 I 1.

Il32Elem 3 .92E+04 0.4 14 3.8 1E+02 0.54735 0. 152482 3.60E-03 3.09E-04 5.44E-03 1.

1133 Elem 5.5 1E+04 0.109 5.85E-r03 2. 1565 2.052537 1.99E-02 1:71E-03 1.03E-0 1 11l34Elem 6.03E+04 0.481 1.3 1E+02 0.52685 0.068078 5.3 3E-03 4.57E-04 3.73 E-03 Il35Elem 5.16E+04 0.307 1.23E+03 7.3 8E-0 1 0.444687 6.39E-03 .5.48E-04 2.09E-02 Rb86 7.29E+0 1 0.0178 6.62E+03 2.3348 2.317823 3.43E-07 2.94E-08 1.84E-06 Cs 134 7.29E+03 0.28 4.63E+04 16.485 16 .21794 2.42E-04 2.08E-05 1.29E-03 Cs 136 2.2 8E+i03 0.392 7.33E+03 2.95 75 2.583 615 1.36E-05 1.16E-06 6.43EF-05 Cs 137 4.35E+03 0.101 3.19E+04 11.266 11. 16967 9.87E-05 8.47E-06 5.30E-04 Cs 138 0 0.4255 1.15E+02 0.465904 0.060067 0.OOE+00 0.OOE+00 0.OOE+00 Total TEDE = ToalTEE 6.29E-01 5.39E-02 6.12E-01

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page (Next Project: Nine Mile Point Nuclear Station Unit. -1 Disposition: ,J/A Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21 C096 0 Case 2: J. Metcalf 12/12/06 Ref.

Case 2-Step 1. Establi~sh Base Activity Concentration The activity released from the core for this step is calculated in Appendix B.

The total activity release calculated as described above is 4.31E6 Ci. The individual radionuclide contributors are provided in Appendix B. The reference concentration is calculated in Appendix C based on this activity being compressed into a section of steam line ID on either side of the detector.

Step 2 - Dose Rate at Main Steam Line Radiation Monitor Location Based on the dose rate analysis is described in Appendix C,the dose rate at the steam line radiation monitor location would be 0.29 radlhr per Ci/m 3 of the CRDA release.

Step 3 - Activijy Concentration Producing. Safety Limit Dose Rate Since the safety limit of the radiation monitor is 3000 mRlhr or -3 rads/hr, the 0.29 rads/hr per Cirm' value means that a concentration greater than 3/0.29 = 10.3 Gu/m3 would be sufficient to terminate mechanical vacuum pump operation. Therefore, a concentration of 10.3 Ci/m3 0.293 Ci/ft3 is assumed in the dose analysis.

Step 4 - Source Volume Needed to Contain Source The source is 4.3 IE6 Ci at a concentration of 0.293 Cu/ff3 . The volume must effectively be 1.47E7 ft3.

Step 5 - Maximum Steam Volumetric Flow for Continued Mec-hanical Vacuum Pump Operation The maximum reactor power and minimum pressure that would be consistent with mechanical vacuum pump operation would be 5% and 300 psia, respectively. The corresponding steam flow is 2.8E5 Ibmi/hr.

The corresponding volumetric flow (with saturated steam specific volume at 300 psia =1.47 ft3/lbm) is:

Steam volumetric flow =2.8E5 lbm/hr x 1.47 fi3/lbm = 4.12E5 cffi = 6860 cfm.

Step 6 - Performn Dose Analysis with RADTRAD and STAIRDOSE For an activity concentration of 0.293 Cu/ff3 and a steam volumetric flow of 6860 cfmn, the activity release rate to the main condenser is:

Activity release rate to the main condenser = 6860 cfr-n x 0.293 Cu/ff3 2.0 1E3 Cu/min.

To release 99% of the activity would require 4.6 inverse exchange rates or:

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page (Next tOriginator/Date Project. Nine Mile Point Nu~clear Station Design Input Compilation and Case 1:H.Pustulka 12/12/06, Case 2; J.Metcalf 12/12/06 Reviewer/Date M. Berg 12/13/06 Unit: I1 aclainN CluainN.Revision H21 C096 Disposition.- P/A 0

Time to release 99% of activity =4.6 x 1.47E7 ft31/6860 cfm = 985 7 min or -164 hours.

The main condenser has a volume of 55,000 ft3 and an exhaust rate using the mechanical vacuum pump of 2000 cfmf. Using these data, an analysis can be set up in which the same activity release as that analyzed in Section I is delivered to a SOURCE control volume with a volume of 1.47E37 ft3 . This volume is then emptied at a rate of 6860 cfm for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The main condenser has a volume of 50,000 ft', and this volume is emptied at a rate of 2000 cfm, also for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A simple spreadsheet can be established to describe the transient normalized activity in the main condenser as an illustration of the release timing. The transient normalized activity in the main condenser is as follows (not considering decay or decontamination in the steam lines):

Normalized Activity in the Main Condenser 1 .20E-02 - ______________________

1.OOE-02 8.OOE-03 4.OOE-03 2.OOE-03 0.OOE+00 0 240 480 720 960 1200 14401 Minutes Since the normalized activity in the main condenser presented in this figure does not consider decay or decontamination in the steam line, it is strictly correct only for a radionuclide like Kr85.

Since there are about 3440 Ci of Kr85 released according to Appendix B, one can expect the 1Q85 activity in the main condenser for the actual dose analysis to peak at about two hours with a level of about 0.011 x 3440 = 38 Ci. The actual result from the STARDOSE analysis at t = 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months is 38.1 Ci of Kr85.

It is evident from the plot of normalized activity in the main condenser that the worst two hours for the EAB dose will be from 1.23 to 3.23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months when the activity in the main condenser is the highest.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page (Next _Al_-)

Project. Nine Mile Point Nuclear Station Unit: -1 Disposition: oi/A Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case '1:H.Pustulka 12/12/06, M. Berg 12/13/06 H21 C096 0 Case 2: J.Metcalf 12/12/06 Ref.

The control room model is similar to that in Case 1. The same steam line and main condenser D~s are applied to this analysis as are applied to the analysis of Case 1. The mechanical vacuum pump is assumed to stop at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , so the duration of release is the same as Case 1..

The power level of 1887 MWt is increased to 3397 M~t for use in RADTRAD and STA.RDOSE.

In this way, the nuclhde inventories used in the "standard" RADTRND and STARDOSE library files (Reference 4, Item 1.2) can be used as-is; and the 1.8 peaking factor is included by using the higher power level.

The DCFs are identified in Item 9.1 and 9.2 of Reference 4.

The input, library, and output files for RADTRAD are presented in Appendix D. The input, library, and output files for STAIRDOSE are presented in Appendix E.

Conclusions For control room operators and for the general public, the radiation dose acceptance criteria for all design-basis accidents are as defined in Reference 1. For the BWIR control rod drop accident, the limits are 5 rem TEDE for Control Room and 6.3 rem TEDE for offsite locations. (For the Control Room, the exposure interval is 30 days with allowance for partial occupancy after the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The EAB dose is based on the worst 2-hour exposure, and the LPZ dose is based on 30-day exposure just as for the Control Room.) The analysis shows that a control rod drop accident will result. in Control Room operator doses and offsite doses to the general public that are below the stated limits.

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Project: Nine Mile Point Nuclear Station Unit: 1 Disposition' WJ Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 121121/06 M.Berg 12/13/06 H21 C096 0 Appendix A: Spreadsheet for the Calculation of Offsite and Control Room Doses Background/Methodology It is desirable for simplicity in many cases to calculate a bounding radiation dose for a given accident using several basic assumptions. These are as follows:

o It is assumed that the release of activity may be defined at the outset (i.e., there are no time-dependent mechanisms that modify the amount of activity that's released; e.g., no delayed filtration).

o It is assumed that the release is instantaneous and complete, and the transport to the receptor is instantaneous, as well. Therefore, no radioactive decay needs to be considered. Note that the activity release, A, may, in fact, occur over a given time duration, t, at a rate Alt. As long as the exposure time is equal to duration of the release, time cancels out of the integrated dose analysis.

o It is assumed that the release is limited to coolant and/or gap activity (i.e., only a limited number of radionuclides are included in the sheet).

o It is assumed that the chemical/physical formn of the iodine as it is released is limited to organic and elemental.

o No credit for control room emergency ventilation (i.e., filtration) is assumed.

o It is assumed that the atmospheric dispersion for the duration of the release may be characterized by a single value of X/Q for each location (EAB, LPZ, and control room).

o It is assumed that the exchange rate of the control room with the environment is infinite so that the concentration of activity inside the control room is equal to that in the atmosphere.

o It is assumed that the breathing rate of exposed individuals is a constant 3.5E-4 mn3 /SeC.

Effectively, this means the release actually must occur over a period of no more than eight hours in order for the LPZ dose not to be overstated.

o It is assumed that the control room occupancy factor is unity.

In addition, for the spreadsheet to be consistent with Reference 1, Dose Conversion Factors (DCFs) based on References 2 and 3 must be used. These are taken from the default TIID.INP and FGR6O.1NP default files of Reference 4. Breathing rates and occupancy factors are taken from Reference 1.

The following section describes the development of such an Excel spreadsheet.

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Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition- O/Li

-calculation No. Revision rOriginator/Date H.Pustuika 12/12//06 Review er/Date M.Berg 12/13/06 H21 C0960 j Spreadsheet Development The spreadsheet is displayed at the end of this section, just before the references.

At the top of the spreadsheet (in the first row) is the title. An example might be "NMPlI MSLB".

In the second row may be found the EAB, LPZ, and control room X/Qs in units of seconds/in 3 The control room volume in ft3 is given in the third column. It is included to provide the basis for the finite volume correction factor for gamma shine dose provided by Reference I (calculated to the right of the control room volume).

The next three rows provide scaling factors that apply equally to all of the radionuclides listed and to all of the calculated doses (EAB, LPZ, and control room). For example, in an FHA analysis, if the core-wide activity available for release is expressed as Ci/MWt, one scaling factor may be the power of the core, a second may be the peaking factor to account for the fact that the speifi acivity inthe affected fuel bundles may be greater than the core average, and the third may be the fraction of the core's activity that is released from the damaged bundles (i.e., the fraction of the core activity assumed to be in the gap multiplied by the fraction of the core fuel bundles that are damaged by the drop). Space is available next to each scaling factor to an-notate what each value represents.

DFs are specifically provided in the next row after the scaling factors. One DF is provided for elemental iodine and one for alkali metals (i.e., Cs and Rb).

The "Source" column (i.e., the second column) has already been mentioned. One space is provided under "Source" to identify the units of "Source". For each of the coolant and/or gap release radionuclides identified in the first column, a "Source" entry may be made.

In the third column, there is a place for scaling factors unique to individual radionuclides. For example, gap fractions that differ from the general gap fraction may be accommodated using these radionuclide-specific scaling factors. If the 1-131 gap fraction is 8% vs. the general value of 5%, then the "Source" for 1-13 1 would have to be increased by a factor of 1.6 to account for that difference. That factor may be entered in the third column.

In the fourth column, the DCFs for immersion dose are provided. As noted previously, these are taken from Reference 4 TTD.INP and FGR6O.IN7P with the multiplication of "Cloudshine-Effective" by 3.7E12 to convert Sv-m 3 /Bq-sec to rem-m 3/Ci-sec. In the fifth column, the "Inhaled-Chronic-Effective" values from FGR6OJINP have been multiplied by the same 3.7E 12 to convert Sv/Bq to rem/Ci. Note that these DCFs include short-lived decay daughters as long as (1) the daughter has a half-life less than 90 minutes and (2) the daughter has a half-life less than

0. 1 times the parent. One exception has been made to this rule. Because of its importance as a

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page ~.A3 (Next __A:4__

Project: Nine Mile Point Nuclear Station Unit: 1 Disposition- P)Aj Originator/Date Reviewer/Date Calculation No. Revision H.Pustuika 12/12//06 M.Berg 12/13/06 H21CO96 70 decay daughter, the DCFs for Rb-88 have been added to those for Kr-88 even though the half-life of Rb-88 (17.8 minutes) is slightly greater than 10% of its parent Kr-88 (170.4 minutes).

In the sixth column, a TEDE DCF is prepared which is the sum of the imnmersion DCF and the inhalation DCF times the assumed breathing rate of 3.5E-4 mn3 /Sec.

In the seventh column, a control room DCF is defined which is similar to the TEDE DCF.

However, the immersion DSF is diminished by the finite volume correction factor defined as the following in Reference 1:

338 DDinjeDDEY.3-1173 For a control room volume of 135,000 ft3, for example, the factor is 0.0462. Note that this factor appears next to the control room volume at the top of the spreadsheet. It is -unity for a control room volume of 1.2E9 ft3 .

The eighth column is the EAR dose, the product of Columns 2, 3, and 6, the three general scaling factors, and the EAR X/Q. Note that if a release of the activity, A, in Column 2 occurs over time, t, the release rate is Alt assuming a unit scaling factor in Column 3. When multiplied by the X/Q, the product is the concentration present at the X/Q location for the time, t (i.e., for the duration of the release). When multiplied by the DCF (Column 6) in units of rem-volume/Ci-time, the result is a dose rate for the duration, t. As long as it is assumed that the exposure duration, t', is the same as release duration, t, then the immersion + inhalation dose is simply the product as just described. In the last row of Column 8, the EAR dose is summed for all radionuclides in Column 1. Note that in calculating the EAR dose, the elemental iodine dose is reduced by the DF for elemental iodine and the alkali metal dose is reduced by the DF for alkali metals.

In Column 9, the Column 8 results are adjusted by the ratio of the LPZ XIQ to the EAR X/Q to obtain the LPZ dose.

Finally, in Column 10, the Column 8 results are adjusted by the ratio of the control room X/Q to the EAR X/Q and by the ratio of the control room DCF to the TEDE DCF to obtain the control room dose contribution for each radionuclide. As with the EAR and the LPZ doses, these are summed at the bottom of column to obtain the total control room TEDE.

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Project. Nine Mile Point Nuclear Station Unit: 1 Disposition: tsý)A Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 12/121/06 M.Berg 12/13/06 H21 C096 0 Ref.

Spreadsheet for Simplified Dose Evaluation TITLE EAB LPZ CR Dispersion (,XIQs) x.xxE-xx x.xxE-xx x.xxE-xx sec/m-3 CR Vol = 1.20E--09 ft) w/ finite volume gamnma, correction =0.999 Scaling Factor 1 = 1 Scaling Factor 2 = I Scaling Factor 3=

DF for Elemental 1 1 DF for Alkali Metals=

Nuclide- WB CEDE TEDE CR EAB LPZ CR Source: Specific DCF DCF DCF DCF TEDE TEDE TEDE Units>>> Scaling rem-m3 remi/Ci remn-m.3 rem-m.3 rem rem rem Nuclide Factor Ci-sec Ci-sec Ci-sec Kr83m 0 1 5.55E-06 0 5.5 5E-06 5.54E-06 0.OOE+00 0.00E+00 0.00E+00 Kr85m. 0 1 0.0277 0 0.0277 0.027666 0.OOE+00 0.OOE+00 0.00E+00 Kr-85 0 1 0.00044 0 0.00044 0.000439 0.OOE+00 0.OOE+00 0.OOE+00 Kr87 0 1 0.152 0 0.152 0.151813 0.OOE+00 0.00E-i00 0.OOE+00 Kr88 0 1 0.501 8.36E+01 0.53026 0.529643 0.OOE+00 0.OOE+00 0.OOE+00 1Q89 0 1 0.323 0 0.323 0.322603 0.OOE+/-00 0.00E-'00 0.00E+00 Xel')lr 0 1 0.00144 0 0.00144 0.001438 0.00E+00 0.OOE+00 0.OOE+00 Xel'33m 0 1 0.00507 0 0.00507 0.005064 0.OOE+00 0.00E+00 0.OOE+00 Xe133 0 1 0.00577 0 0.00577 0.005763 0.OOE-i00 0.OOE+00 0.OOE+00 Xel35mn 0 1 0.0755 0 0.0755 0.075407 0.OOE+00 0.OOE+/-00 0.OOE+00 Xel35 0 1 0.044 0 0.044 0.043946 0.OOE+00 0.OOE+00 0.OOE+00 Xel137 0 1 0.0303 0 0.0303 0.030263 0.OOE+00 0.OOE+00 0.OOE+00 Xe138 0 1 0.213 0 0.213 0.212738 0.OOE+00 0.OOE+O0 0.OOE+00 Il3l0rg 0 1 0.0673 3.29E+04 11.5823 11.58222 0.OOE+00 0.OOE+00 0.OOE+00 11320rg 0 1 0.414 3.81E+02 0.54735 0.546841 0.OOE+00 0.OOE+/-00 0.OOE+00 11330rg 0 1 0.109 5.85E+03 2.1565 2.156366 0.OOE+00 0.OOE+00 0.OOE+00 11340rg, 0 1 0.481 1.3 1E+02 5.27E-0 1 0.526258 0.OOE+00 0.OOE+00 0.OOE+/-00 Il350rg 0 1 0.307 1.23E+03 0.7375 0.37122 0.OOE+00 0.OOE+00 0.OOE+/-00 1l31Elem 0 1 0.0673 3.29E+04 11.5823) 11.58222 0.OOE+00 0.OOE+00 0.OOE++/-00 Il32Elem. 0 1 0.414 3.8 1E+t02 0.54735 0.546841 0.OOE+00 0.OOE+/-00 0.OOE+/-00 Il33Elemn 0 1 0.109 5.85E+03 2.1565 2.156366 0.OOE+00 0.OOE+00 0.OOE+00 Jl34Elem 0 1 0.481 1.31E+02 0.52685 0.526258 0.OOE+00 0.OOE+00 0.OOE+/-00 Il35FIemn 0 1 0.307 1.23E+03 7.38E-01 0.737122 0.OOE+00 0.OOE+/-00 0.O0E4-00 Rb86 0 1 0.0178 6.62E+03 2.3348 2.334778 0.OOE+/-00 0.OOE+00 0.OOE+/-00 CsI34 0 1 0.28 4.63E+04 16.485 16.48466 0.OOE+00 0.OOE+00 0.OOEi-00 Cs136 0 1 0.392 7.33E+03 2.9575 2.957018 0.OOE+00 0.OOE+00 0.OOE+/-00 Cs137 0 1 0.101 3.19E+/-04 11.266 11.26588 0.OOE+00 0.OOE+/-00 0.OOE-i00 Cs138 0 1 0.4255 1.15E+02 0.465904 0.46538 0.OOE+/-00 0.OOE+00 0.OOE+/-00 Total TEDE TotalTEDE O.OOE+OO O.OOE+OO 0.OOE+0O

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Project: Nine Mile Point Nuclear Station Unit: 1 Disposition: tal&

Originator/Date IReviewer/Date Calculation No. Revision H.Pustulka 12/12106 M.Berg 12/13/06 H21 C096 0 Ref.

References A- I Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluat ing Design Basis Accidents at Nuclear Power Reactors", July 2000 A-2 K.F. Eckerman et at., "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," Federal Guidance Report 11, EPA-520/1-88-020, Environmental Protection Agency, 1988.

A-3 K.F. Eckerman and J.C. Ryman, "External Exposure to Radionuclides in Air, Water, and Soil,"

Federal Guidance Report 12, EPA-402-R-93-08l, Environmental Protection Agency, 1993 A-4 NIJREG/CR-6604, "RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", December 1997

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page-B 1 (Next _62-Project: Nine Mile Point Nuclear Station Unit: -1 Disposition:, _ý Origi.nat.or/Date Reviewer/Date Calculation No. -Revision H.Pustulka 12/12/06 M.Berg 12/13/06 H21CO96 00 Appendix B- Calculation of Reference Activity Release for Main Steam Line Radiation Monitor Gamma Dose Calculation Objective In this appendix, the activity release is calculated for a CRDA with a peaking factor of 1.8, a power level of 1887 MWt, and release fractions from Item 2.14 of Reference 4 of the main body of the calculation.

Calculation The calculation is done using the following spreadsheet. The radionuclides are identified in the first column. In the second column, the fraction of the core released is given. The values from this column are calculated by multiplying the failed fuel fraction (2.5 8%) by the group specific release fraction from the gap to the coolant. Note, too, that the iodine is broken down into 3%

organic and 97% elemental. As an example, the release fraction for elemental 1131 is calculated using, the following:

(2.58%)*(l0%)*(97%)= 2.50E-03 In the third column, the Ci/MW(t) are the core inventories taken from Item 1.2 of Reference 4 of the main body.

These are multiplied by the power level of 1887 MWt and the peaking factor of 1.8 to obtain the fourth column. The total of the fourth column total is 4.3 1E+06 Ci. The last column is the percentage of the total Ci.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -B2-(Next -C1 Project. Nine Mile Point Nuclear Station Unit: -I Disposition- raLk Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 12/12/06 IM. Berg 12/13/06 H21CO96 1 Nudlide Rel FraCt Ci/MWt Ci Percentage Kr83m 2.58E-03 3.27E+03 2.87E+04 0.665%

Kr85m 2-58E-03 6.82E+03 5.98E+04 1.387%

Kr85 2.58E-03 3.93E+02 3.44E+03 0.080%

Kr87 2.58E-03 1.30E+04 1.14E+05 2.644%

Kr88 2.58E-03 1.83E+04 1.60E+05 3.722%

Kr89 2.58E-03 2.22E+04 1.95E+05 4,515%

Xe131m 2.58E-03 3.04E+02 2.66E+03 0.062%

Xe133m 2.58E-03 1.63E+03 1.43E+04 0.331%

Xe133 2.58E-03 5.27E+04 4.62E+05 10.718%

Xel35m 2.58E-03 1.09E+04 9.55E+04 2.217%

Xe1 35 2.58E-03 1.91E+04 1,67E+05 3.884%

Xe137 2.58E-03 4.80E+04 4.21 E+05 9.762%

Xe138 2-58E-03 4.50E+04 3.94E+05 9,152%

1131 Org 7.74E-05 2.71 E+04 7.12E+03 0.165%

11 320rg 7.74E-05 3.92E+04 1.03E+04 0.239%

11 330rg 7.74E-05 5.51 E+04 1.45E+04 0.336%

11 340rg 7.74E-05 6.03E+04 1.59E+04 0.368%

11 350rg 7.74E-05 5.16E+04 1.36E+f04 0.315%

1131 Elem 2.50E-03 2.71 E+04 2.30E+05 5.346%

Il32EIem 2-50E-03 3.92E+04 3.33E+05 7.733%

Il33EIem 2.50E-03 5.51 E+04 4.68E+05 10.870%

1134E~em 2,50E-03 6.03E+04 5,13E+05 11.895%

11l35Elem 2,50E-03 5.16E+04 4.39E+05 10.179%

Rb86 3,10E-03 7.29E+01 7.67E+02 0.018%

Cs134 3.1 OE-03 7.29E+03 7.67E+04 1.779%

Cs136 3.10OE-03 2.28E+03 2.40E+04 0.556%

Cs137 3.1OE-03 4.35E+03 4.57E+04 1.062%

Total 4.31 E+06

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: io/A Originator/Date Reviewer/Date Cluaio No. Revision H.Pustulka 12/12/06 M.Berg 12/13/06 H2C96 0 Ref.

Appendix C: Steam Line Radiation Monitor Response [Manual Calculation]

The following spreadsheet is used to determine the steam line radiation monitor response. All input is shown boxed. The geometry is from the design input section of the main body of the calculation. The activities for the key radionuclides are from Appendix A (for a peaking factor of 1.8 as used in the dose analysis). The MeV/dis values are from Reference C-1. In the columrns to the right of the input MeV/dis, the corresponding values for MeV/sec are obtained by multiplying by the "Tot Ci Rel" and 3.7E10 disintegrations per Ci. These are summed in the row "Totals"; and in the following row, the gamma power per unit volume is obtained by dividing the sums by 2 (to obtain the "per steam line" value) and by the single steam line volume in in'.

Note that only I diameter on each side of the detector is used to define the steam line concentration since the concentration is arbitrary (the monitor response being normalized by Ci/m 3 ) . The steam line volume is calculated in the first column just below the entered geometry information; and j ust below it, the single steam line activity concentration is calculated from the total 4.3 1E6 Ci released, divided by 2 for the "per steam line" value, and divided by the volume.

Emnitted Energy MeV/dis* MeV/dis* MeV/dis* MeV/dis* MeV/sec Me V/sec Me V/sec Me V/sec Tot Ci Rel 0.5-1 MeV 1-1.5 MeV 1.5-2 MeV 2+MeV 0.5-1 MeV 1-1.5 MeV 1.5-2 MeV 2+MeV SL: Kr83m 2.87E+04 0 0 0 D 0 0 0 0 L 1.22 Kr85mn 5,98E+04 0.00012 0 0 0 2,65E+1 1 0 0 0 OD (in)=2 Kr85 3.44E.*03 0.0022 0 0 0 2.84E+1 1 0 0 0 Wall (in)= 12 lKr87 1.14E-'05 0.083 0.028 0.0579 0.425 3.51E+1 4 1.16E+14 2.44 E+14 1.79E+15 Vol (m3) = 0.287499 Kr-88 1,60E-'O5 0.140 0.111 0.223 1.41 8.31 E+1 4 6.59E+14 1.32E+15 8.37E+15 1 SL Conc Kr89 1.95E+05 0.377 0.284 0.335 0.7 2.71 E+1 5 2.04 E+15 2.41 E+15 5.04 E+15 (Ci/m3) = 7.49E+06 Xel 31nm 2.66E-t03 0 0 0 0 0 0 0 0 (assuming all activity Xel 33m 1.43E-+04 0 0 0 0 0 0 0 0 intwo 1D lengths) Xe133 4.62E+s05 0 0 0 0 0 0 0 0 Xel35m 9.55E+044 0.427 0 0 0 1.51E+1 5 0 0 0 Xe135 1,67E+05 0.019 0 0 0 1.18E+14 0 0 0 Xe137 4.21 E+05 0.0072 0.024 0.0109 0.00516 1,13E'-14 3.67E+14 1.7E+14 8.03E+1 3 Xe1 38 3.94E+0A~5 0.032 0,062 0.344 0.462 4.64E+14 8.99E+14 5.02E+~1 5 6.74E+1 5 1131 2.37E+i05 0.063 0 0 0 5.49E+14 0 0 0 1132 3.441E+05 1.890 0.314 0.028 0.0376 2.4E+16 3.99E+1 5 3.56E+1 4 4.78E+/-14 1133 4.83E+05 0.545 0.058 0 0 9.74E+15 1.04 Ei15 0 0 1134 5.28E+05 1.860 0.391 0.272 0.0173 3.64E+16 7.64E+15 5.32E+/-15 3.38E+1 4 1135 4.52E+05 0.130 0.933 0.42 0.0546 2.17E+15 1.56E+16 7.03E+15 9.13E+14

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Project: Nine Mile Point Nuclear Station Unit: caultoN. Disposition: %1/

Originator/Date Reviewer/Date Caclto oRevision IH. Pustulka 12/12/06 M.Berg 12/13/06 H21C09610 Ref.

Rb86 0 0.095 D 0 0 2.68E÷1 2 0 0 Cs 134 1.470 0.073 0 0 4.1 7E+1 5 2.07E+1 4 0 0 Cs 136 0.824 1.080 0 0 7.31 E+1 4 9.58E+/-1 4 0 0 Cs137 0.563 0 0 0 9.53E+14 0 0 0 Totals 4.31 E-v06 8.48E+1 6 3.35E+1 6 2.19 E+'16 2.37 E-+16 Gamma power per unit volume for one steam line 1.47E+17 5.83E-1 6 3.80E+1 6 4.13E+16 MeV/sec-m3 SL rad = 0.273812 m SL area = 1.720412 m2/m (inside surface)

SL vol 0.235535 m3/m Surface = 7,304282 m21m3 (unit surface area/ unit vol) =73042.82 cm2Im3 Treating SL as infinite line source, surface gamma energy flux = 2.02E+1 2 7.98E+1 1 5.21 E+1 1 5.65E+1 1 MeV/sec-cm2 For 1/R, at 066 m from SL centerline, flux decreases to 8.83E+1 1 3.49E+1 1 2.28E+1 1 2.47E+1 1 MeV/sec-cm2 Shield thickness 3.0988 cm (wall thickness)

Attenuation coefficients (for iron, including buildup from Ref C-2) F 0.42 0.33 0.27 0.23 cm -1 Attenuated flux = 2.4E+1 1 1.26E+1 1 9.86E+10 1.21 E+1 1 MeV/sec-cm2 Total attenuated flux, one intinite steam line, concentration 7.49E+-06 Ci/m3= 5.86E+1 1 MeV/sec-cm2 or = 3.37E+09 erg/hr-cm2 Absorbed Dose Absorption. coefficient for air = 1 0.0636 cm2/g for 1,0 MeV photons (from Ref C-3)

Absorbed dose rate, one infinite steam line, concentration = 7.49E+06 Ci/m3 2.15E-+08 erg/hr-g or = 2.15E+06 rads/hr Absorbed dose rate I Ci/m3 (for one infinite steam line, concentration 7.49E+0A6 Ci/m3) = 2.86E-01 rad s/hr /Ci/m3 This isfor an infinite steam line representing an approximation of a steam line extending -1 to 2 D on either side of the detector.

To refine this approximation for the actual geometry, one may assume that the dose rate to the detector varies as 1/d12, where d12 is the sum of R12 (distance from the detector to the SL centerline) and xA12(distance along the SL axis).

The integral of 1/(R A2+xA 2)along the SIL axis is(1/R)arctan(x/R). Inthe limit from x = 0tox=infinity, this integral isequal to piI2R or 1.57/R.

On the side ofthe detector where the SL extends 0.95 diameters (i.e., 1.9R), the integral equals 1,09/R.

On the side of the detector where the SL extends 2.05 diameters (i.e., 4.1 R), the integral equals 1.33/R.

The average is 1.211R or 77% of the semi-infinite integral of 1.57/R.

Therefore, the response calculated above for the infinite SL isadjusted to 77% of the 0.286 radslhr / Cim3 or 0.22 radslhr / Cim3.

ENIERN EVCSCALCULATION CONTINUATION SHEET Page _C3_

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: m/Lp Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 12/12/06 M.Berg 12/13/06 H21C096 0 Ref.

It isalso the case that each detector can see the other steam line. The distance to the other steam line is about three times greater, thus, one may estimate an increase inthe detector response of -30%~tor the other line (-I/Rfor a line source).

The overall response then = -0.29 rads/hr / Ci/cm3.

From Reference c-1 Continuing the calculation, the steam line inside radius is calculated (in meters) as well as the inside surface area and the steam line volume per unit length as well as the surface area per unit volume (in cm_2/m3). Treating the steam line as an infinite line source, the gammna energy flux at the surface (before attenuation in the pipe wall shield) is calculated by dividing the photon energy-dependent gamma power per unit volume by the unit surface are per unit volume (to obtain MeV/sec-cm 2). In the following row, this flux is reduced by I/R from 0.2738 12 mn to 0.626 mn. Calculating the pipe wall thickness as a shield (3 .0988 cm) and using the attenuation coefficients for iron from Figure 7-1 of Reference C-2, one obtains the attenuated flux by multiplying the unattenuated flux by exp(-coefficient cm-' x 3.0988 cm). These are then summed to obtain the total value of 5.86E1 I MeV/sec-crn 2 . This is converted by multiplying by 5.76E-3 to erg/hr-cm2 .

To obtain the air dose in rads/hr, the total attenuated energy flux is multiplied by the absorption coefficient for air taken from Reference C-3 to obtain the ergs/hr-gram of air; and then this is converted to rads/hr using 100 ergs/gram air per rad. Finally, this value is divided by the concentration in a single steam line (7.49E6 Ci/m') to obtain the dose rate per unit Ci/m'; i..e., 0.286 rads/hr per Ci/m'. This value is then further adjusted as described to account for the finite length of steam line and the presence of the second steam line. These almost exactly compensate for one another, so the final monitor response is estimated to be 0.29 rads/hr per Ci/m 3.

ENIERN EVCSCALCULATION CONTINUATION SHEET Page -C4__

(Next D1 Project.: Nine Mile Point Nuclear Station Unit: -1 Disposition:

Originator/Date Reviewer/Date -- Calculation No. Revision H.Pustulka 12/12/06 M.Berg 12/13/06 H21C096 0 L _

Ref.

References:

C-1 Memorandum to File from James Metcalf "Generalization of Spreadsheet Methodology for Comparing TIiD-14844 and AST Gamma Shine Dose Potential", July 27, 2003 0-2 C. F. Bonilla, Nuclear Engineering, McGraw-H-ill, 1957 0-3 J. Wing, "Post-Accident Gas Generation from Radiolysis of Organic Materials", NUREG-1081, September, 1984

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page-D1-(Next -D2 -

Project.' Nine Mile Point Nuclear Station Unit: -1 Disposition- LýA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21CO96 0 Ref.

Appendix D: RADTRAD CRDA Dose Analysis for Case 2 Approach Application of the AST to the NMP CRDA analysis involves the following steps:

Review Regulatory Guide 1.183 (Reference D-l) to ensure that methods being applied to the NMvP LOCA analysis conformn to the requirements of that document.

Using the calculated removal rates and other input data compiled in Reference D-2, prepare a RADTRAD (Reference D-3) analysis of the NIVP LOCA radiation doses for offisite (EA-B and LPZ) as well as for control room.

" Obtain the dose contribution to control room personnel from radiation sources outside the control room.

Prepare an independent review of the overall AST dose analysis (Appendix E).

Model The activity release can be simplified to the model shown in Figure D-lI below.

Figure D-1: CRDA Case 2 Model Environment Control Room 3 ~(CR)4 Volumes:

Source: 1.470E+07 Main Condenser (MC): 5.OOOE+04 Control Room (CR): 1.350E+05 Junctions:

___ Pathway Description 1 Source 4* MC 6.86E+03 cfm for 24 hrs 2 MC 4~ Environment 2.OOE+03 cfm- for 24 brs 3 Environment-4 CR IlE+06, or infinite flowrate into the control room is credited per Assumption 3

______in the main body of this calculation.

4 CR4 Environment IlE+06, or infinite flowrate out of the control room is credited per

_____ _________________Assumption 3 in the main body of this calculation

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D2_

(Next 0D3 Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition: W.A Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H210C096 0 The dose calculation model consists of four control volumes representing the Source, Main Condenser (MC), Environment, and the Control Room (CR).

Control volumes are arranged as shown on Figure D-lI with the various junctions that connect them.

These junctions are associated with volumetric flows which determine the rate at which radioactivity is exchanged between the control volumes. In addition, removal processes such as sedimentation in pipes and filtration are modeled within and between the control volumes, as appropriate.

The RADTRAD computer code is used to perform this dose calculation.

Input Files Plant Scenario File (psJ)

Each RADTRA.D runs uses a specific main input file (.PSF). This file contains most of the key information related to the run: control volumes, junctions, filter efficiencies, XI/Qs etc.

Nuclide Information File (nij The 60 isotopes used in RADTRAD are listed in the nimp,1 ntf file. One will find the radionuclide tnventories listed as Ci/M/Wt in this file.

Release FractionFile (rfi):

The file N.MPlI-crda.rft was used. This file contains information specific to the AST source term, i.e., the fraction and timing of each release phases. A delay of two minutes is credited.

Dose Conversion FactorsFile (inp)

The Dose Conversion Factors file used for thtis RADTRAD run is based on the Federal Guide Reports I I and 12. The file used is l006fgrnmpl.inp. This file is a modification of the default RADTRAD file called FGR11&12.1N'P to include Rb88.

Results:

Case 2

__________RADTRAD EAB 0.342 LPZ 0.211 Control Room 1.61

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D3-(Next _D4 Project. Nine Mile Point Nuclear Station Unit.- 1- Disposition:, 1_1A Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H210C096 0 Appendix D-1: Primary Input (.psf) file, Plant Scenario File, NMPICRDA.psf Radtrad 3.02 1/5/2000 Nuclide Inventory File:

c:\program files\u s nuclear regulatory commission\radtrad 3.02a\defaults\nmpl nif Plant Power Level:

3.3970E+03 Compartments:

4 Compartment 1:

Source 3

1.4700E+07 0

0 0

Compartment 2.

MC 3

5.0000E+04 0

0 0

Compartment 3:

CR 1.3500E+05 0

0 0

Compartment 4:

Environment 2

0.OOOOE+00 0

0 0

Pathways:

4 Pathway 1:

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D4-(Next -D5 -

Project: Nine Mile Point Nuclear Station Unit: 1 Disposition- O/A~

Originator/Date Reiwer/Date Calculation No. Revisi-on j J.Metcalf 12/12/06 Apendix E IH21C096 0 Ref.

Source to MC 1

2 Pathway 2:

MC to Environment 2

4 1

Pathway 3:

Environ ment to CR 4

3 2

Pathway 4:-

CR to Environment 3

4 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1.OOOOE+OO c:\program files\u s nuclear regulatory commission\radtrad 3.02a\defaults\1 OG6fgrnmpl .inp c:\program files\u s nuclear regulatory commission\radtrad 3.02a~defaults\nmp 1-crda. rft 0.OOOOE +00 1

0.OOOCE-'00 9.7000E-01 3.OOOOE-02 11.OOOOE+00 Overlying Pool.

0 0.OOOOE+00 0

0 0

0 Compartments:

4 Compartment 1:

0 0

0

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D5_

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Project:- Nine Mile Point Nuclear Station Unit: 1- Disposition: 0JA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21 0096 0 Re-f.

0 0

0 Compartment 2:

0 0

Compartment 3:

0 0

0 Pathways:

4 Pathway 1:

0 0

3 0.OOOOE+0O 1.OOOOE+02 6.8600E+03 2.4000E+01 1.OOOOE+00 0.OOOOE+00 7.2000E+02 1.OOOOE+00 0.OOOOE+00 3

0.OOOOE+00 1.OOOOE+01 6.8600E+03 2.4000E+01 1.OOOOE+00 0.OOOOE+00 7.2000E+02 1.OOOOE+00 0.OOOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D6-(Next N7-Project.' Nine Mile Point Nuclear Station Unit: -1 Disposition.- rVA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/121206 Appendix E H21CO96 0 Ref.

3 O.OOOOE+OO 1.COOOE+O1 6.8600E+03 2.4000E+01 1.COOOE+OC O.OOOOE+OO 7.2000E+02 1.OCOOE+OO O.OCOCE+OO 0

0 0

Pathway 2:.

0 0

1 3

0.OOOOE+00 1.OOOOE+02 2.OOOOE+03 2.4000E+01 1.OOOOE+00 0.OOOOE+00 7.2000E+02 1.OOOOE+00 0.OOOOE+00 3

0.OOOOE+00 1.OOOOE+01 2.OOOOE+03 2.4000E+01 1.OOOOE+00 0.OOOOE+00 7.2000E+02 1.OOOOE+00 0.OOOOE+00 1

3 0.OOOOE+00 1.OOOOE+01 2.OOOOE+03 2.4000E+01 1.OOOOE+00 0.OOOOE+O0 7.2000E+02 1.OOOOE+00 0.OOOOE+00 0

0 0

Pathway 3:

0 0

0 1

2 0.OOOOE+00 1.OOOOE+06 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

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1 Project. Nine Mile Point Nuclear Station Unit: -1 Disposition: M/P.

Originator/Date Reviewer/Date Calculation No. Revision 1 J.Metcalf 12/12/06 Appendix E H21CO96 10 Ref. I 0

0 0

Pathway 4:

0 0

0 1

2 0.OOOOE+00 1.OOOOE+06 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 4

3 0.OOOOE+00 5.9800E-05 8.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 1

4 0.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 0

Location 2:

LPZ 4

7 0.OOOOE+00 1.2600E-06 1.2300E+00 2.1 200E-05 5.2300E+00 1.2600E-06 8.OOOOE+00 8.4000E-07 2.4000E+01 3.4500E-07

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Project. Nine Mile Point Nuclear Station Unit: -1 Disposition: r0 )k Originator/Date Reviewer/Date No.

-Calculation Revision J.Metcalf 12/12/06 Appendix E H21CO96 0 9.6000E+01 1.1 100E-07 7.2000E+02 O.OOOOE+CO 4

O.OOGOE-4-G 3.5000E-04 8.OOOOE+OO 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+OO 0

Location 3:

CR 3

0 2

0.OOOOE+0O 3.5000E-04 7.2000E+02 0.OOOOE+00 4

0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 Effective Volume Location:

7 0.OOOOE+00 1.2600E-04 1.2300E+00 2.2700E-04 3.2300E+00 1.2600E-04 8.OOOOE+O0 4.3000E-05 2.4000E+01 3.5800E-05 9.6000E+01 2.5900E-05 7.2000E+02 0.OOOOE+00 Simulation Parameters:

0 Output Filename:

C:\Program Files\U S Nuclear Regulatory Commission\Radtrad 3.o9 0

0 End of Scenario File

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Project.- Nine Mile Point Nuclear Station Unit: 1I Disposition: t4/

Originator/Date Reviewer/Date CluainNo, Revision J.Metcalf 12/12/06 Appendix E H21 C0960 Appendix D-2: Secondary Input (.nif, .rft, .inp) files Appendix D-2.1: Nuclide Information File, nmp.nif Nuclide Inventory Name:

ST general Power Level:

0.1 000E+01 Nuclides:

63 Nuclide 001:

Kr-83m 0.6696E+404 0.8300E+02 3.270E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

Kr-85m 0.161 2800000E+05 0.8500E+02 6.82E+03 Kr-85 0.2100E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 003:.

Kr-85 0.33861 3048E+09 0.8500 E+02 3.93E+02 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-87 0.4578000000E+04 0.8700E+02 1.30E+04 Rb-87 0.1000E+01 none 0.OOOOE+00 none 0.O0OOE+00 Nuclide 005:

Kr-88

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D1 0 (Next _D11 Project: Nine Mile Point Nuclear Station Unit:. 1- Disposition: N/A.

Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H210C096 0J 0,1022400000E+05 0.8800E+02 1.83E+04 Rb-88 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 006:

Rb-86 3

0.161 2224000E+07 0.8600E+02 0.729E+02 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 007:

Rb-88 3

0.1 062000000E+04 0.8800E+02 1.OOOE-06 none 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 2.45E+04 none 0.OOOOE+00 none 0.OOOOE+00 none Q.OOOOE+00 Nuclide 009:

Sr-90 5

0.91895731 20E+09 0,9000E+02 3.14E+03 Y-90 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 010:

sr-91 0.3420000000E+05 0.9100OE+02 3.10E+04

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D1 1 (Next -D12 Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: 01A/,

Originator/Date Reiwer/Date Calculation No. Revision J. Metcalf 12/12/06 Apendix E H21CO96 0 Ref.

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 3.38E+04 Y-92 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Y-90 7

0.2304000000E+06 0.9000E+02 3.24E+03 none 0.0000E+00 none 0.0000E+00 none 0,0000E+00 Nucilde 013:

Y-91 7

0.5055264000E+07 0.91 00E+02 3.18E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 014:

Y-92 7

0.1274400000E+05 0.9200E+02 3.40E+04 none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nudide 015:

Y-93 7

0.3636000000E+05 0.9300E+02 3.96E+04 Zr-93 0.1000E+01 none 0.0000E+00 none 0.0000E+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D12 (Next -D132 E

Project:- Nine Mile Point Nuclear Station riginator/Date J.Metcalf 12/12/06 Reviewer/Date Appendix E Unit: -1 Calculation No.

H21C096 Disposition: WJ4K Revision 0

Nuclide 016:

Zr-95 7

0.5527872000E+07 0.9500E+02 4.46E+04 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none 0.0000E+00 Nuclide 017:

Zr-97 7

0 .6084000000E+05 0.9700E+i02 4.51 E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018.

Nb-95 7

0.3036960000E+07 0.9500E+02 4.48E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nucilde 019:

Mo-99 6

0.2376000000E+06 0.9900E+02 5.13E+04 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none 0.0000E+00 Nuclide 020:

Tc-99m 6

0.21 67200000E+05 0.9900E+02 4.49E+04 Tc-99 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 021:

Ru-103 6

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Project:-Nine Mile Point Nuclear Station Unit: -1 Disposition: 'WJA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E IH21C096 10j Ref.

0.3393792000E+07 0, 1030E+03 4.29E+04 Rh-103m 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Ru-lOS 6

0.1 598400000E+05 0.1050E+03 3.01 E+04 Rh-lOS 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 023:

Ru-106 6

0.3181248000E+08 0,.1060E+03 1.76E+04 Rh-106 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 024:

Rh-105 6

0.1272960000E+06 0.1050E+03 2.84E+04 none 0.OOOOE+00 none 0.0000E+0O none 0.OOOOE+0O Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 3.01 E+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 0.891 E+04

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Project. Nine Mile Point Nuclear Station Unit: Disposition: OJA Onginator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21 C096 703 Ref.

Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 3.OOE+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 028:

Te-1 27m 4

0.941 7600000E+07 0.1270E+03 4.05E+02 Te-127 0.9800E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 029:

Te-129 4

0.41 76000000E+04 0.1 290E+03 8,76E+03 1-129 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuolide 030:

Te-1 29m 4

0.2903040000E+07 0.1290E+03 1.30E+03 Te-129 0.6500E+00 1-129 0.3500E+00 none 0.OOOOE+00 Nuclide 031:

Te-131m 4

0.1 080000000E4-06 0.13 10E+03 3.97E+03 Te-131 0.2200E+00 1-131 0,7800E+00 none 0.OOOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D1 5 (Next __D16_

Project., Nine Mile Point Nuclear Station Unit: -1 Disposition: OAL originator/Date Reviewer/Date Calculation No. Revi-sion J.Metcalf 12/1 2/06 Appendix E H210C096 00 Nuclide 032:

Te-132 4

0.28 15200000E+06 0.1 320E+03 3.85E+04 1-132 0.1000E+01 none 0.0000E+/-00 none 0.0000E+00 Nuclide 033:

1-131 2

0.6946560000E+ 06 0.13 10E+03 2.71 E+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 3.92E+04 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nudlide 035:

1-133 2.

0.7488000000E+05 0.1330E+03 5.51 E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nudlide 036:

1-134 2

0.31 56000000E+04 0.1340E+03 6.03E+04 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 037:

1-135 2

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D16-(Next 0D17_

Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: O./A.

Originator/Date IReviewer/Date -CalculationNo. Revision J.Metcalf 12/12/06 LAppendix E H21 0096 0 Ref.

0.2379600000E+05 0.1350E+03 5.1 6E+04 Xe-i 35m 0.1 500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 038:

Xe-133 0.4531680000E+06 0.1330E+03 5.27E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 039:

Xe-i 33m 1

0.1926720000E+06 0.1330E+03 1.63E+03 Xe-133 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nudlide 040:

Xe-135 1

0.3272400000E+05 0.1 350E+03 1.91 E+04 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 041:

Xe-i 35m 0.91 800000E+03 0.1350E+03 1.09E+04 Xe-135 0.9940E+00 Cs-135 0.6000E-03 none 0.OOOOE+00 Nuclide 042:

Xe-138 1

0.85200000E+03 0.1 380E+03 4.50E+04

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D1 7-(Next _D18 Project: Nine Mile Point Nuclear Station Unit: Disposition.- WA, Originator/Date ReviewerlDate Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21CO96 0 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 043:

cs-134 3

0.65071771 20E+08 0.1340E+03 7.29E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 044:

Cs-i 36 3

0.1 131840000E+07 0.1360E+03 2.28E+03 none 0.0000E+00 none 0.OOOOE+00 none 0,OOOOE+00 Nudlide 045:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.35E+03 Ba-137m 0.9500E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nudide 046:

Ba-139 5

0.4962000000E+04 0.1390E+03 4.89E+04 none 0.OOOOE+00 none 0,OOOOE+00 none 0.OOOOE+00 Nuclide 047:

Ba-140 5

0.1 100736000E+07 0.1400E+03 4.71 E+04 La-140 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D18-(Next _D19)

Project: Nine Mile Point Nuclear Station Unit: __1- Disposition.- -!qL Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21CO96 0 Nudlide 048:

La- 140 7

0.1 449792000E+06 0.1 400E+03 5.12E+04 none 0.0000E+00 none 0-0000E+00 none 0.OOOOE+00 Nudlide 049:

La- 141 9

0.141 4800000E+05 0.141 OE+03 4.45E+04 Ce-141 0.1000E+01 none 0-OOOOE+00 none 0.OOOOE+00 Nuclide 050:

La-142 7

0.5550000000E+04 0.1 420E+03 4.29E+04 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nudlide 051:

Ce- 141 8

0.2808086400E+07 0.1410E+03 4.47E+04 none 0.OOOOE+00 none 0.OOOOE+00 none 0-OOOOE+00 Nuclide 052:

Ce- 143 8

0.1188000000E+06 0.1430E+03 4.11IE+04 Pr-143 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 053:

Ce-144 8

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Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition: OIPA O~ginator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21C096 To 0.,2456352000E+08

0. 1440E+03 3.70E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.0000E+00 Nudlide 054:.

Pr-143 9

0.1 171584000E+07 0.1 430E+03 3.97E+04 none 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 055:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.80E+04 Pm-147 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nudlide 056:

Np-239 8

0.2034720000E+06 0.2390E+03 5.78E+05 Pu-239 0.1000E+01 none 0,OOOOE+00 none 0.0000E+00 Nudlide 057:

Pu-238 8

0.2768863824E+1 0 0.2380E+03 1.45E+02 U-234 0.1000E+01 none 0.0OOOE+00 none 0.OOOOE+00 Nudlide 058:

Pu-239 8

0.7594336440E+1 2 0.2390E+03 1.34E+01

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D20-(Next 021 Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: 0~/k~

Originator/Date -Reviewer/Date Caclton N Revision J.Metcalf 12/12/06 Appendix E H1 96 0 U-235 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 059:

Pu-240 8

0.2063867E+1 1 0.240E+03 1.89E+01 U-236 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 060:

Pu-241 8

0.473364E+09 0.241 E+03 5.49E+03 Am-241 0.1000E4-01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 061:

Am-241 7

0.13664441E+1 1 0.24 1E+03 7.48E+00 Np-237 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 062:

Cm-242 7

0.1 4083200E+08 0.242E+03 1.85E+03 Pu-238 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 063:

Cm-244 7

0.564881 04E+09 0.244E+03 1.23E+02 Pu-240 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: t.NA Originator/Date Reviewer/Date Calculation No, Revision J.Metcalf 12/12/06 Appendix E H21C096 J03 Ref.

IEnd of Nuclear Inventory File

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D22-(Next _D23 -

Project., Nine Mile Point Nuclear Station Unit: 1- Disposition: WA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21C096 0 Ref.

Appendix D-2.2: Release Fraction File, NMPI-crda.rft Release Fraction and Timing Name:

NMP1 - CRDA with no fuel melting Duration (h): Control Rod Drop Accident 0.001 0D+00 0.0000D+00 0.0000D+00 0.0000D+00 Noble Gases:

2.5800E-03 0.0000E+00 0.0000E+00 0.0000E+00 Iodine:

2.5800E-03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Cesium:

3.1000E-03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Tellurium:

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Strontium:

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Barium:

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Ruthenium:

0.OOOOE+00 0.0000E-i00 0.OOOOE+00 0.OOOOE+00 Cerium:

0.OOOOE+00 0.OOOOE+00 0.00002+00 0.0000E+00 Lanthanum:

0.0000E+00 0.O000E+00 0.0000E+00 0.OOOOE+00 Non-Radioactive Aerosols (kg):

0.00002+00 0,00002+00 0.00002+00 0.00002+00 End of Release File

ENGINEERING SERVICES I'AI~ IA If%& I F^F^IkIM#h II I A .Uý&S I~ ^- I-'nI 14 Ir ~ Page _D23 CALCLI~JLA I IVP4 tsUN I INUIA I 1UN I(Next _D24 Project.' Nine Mile Point Nuclear Station Unit: -1 Disposition: OiA.

Originator/Date Reiwer/Date Calculation No. Revision J.Metcalf 12/12/06 Apendix E H21CO96 0 Appendix D-2.3: Dose Conversion Factor File, 1OO6fgrnmpl.inp FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 Implicit daughter halflives (in)less than 90 and less than 0.100 of parent 9 ORGANS DEFINED INTHIS FILE:

GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 63 NUCLIDES DEFINED INTHIS FILE:

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Rb-86 D Rb-88 D Sr-89 Y Sr-90 Y Sr-91 Y lncluding:Y-91m Sr-92 Y Y-90 Y Y-91 Y.

Y-92 Y

~Y-93 Y Zr-95 D Zr-97 Y lncluding:Nb-97m Including Nb-97 Nb-95 Y Mo-99 Y Tc-99m D Ru-1 03 Y Including: Rh-1 03m Ru-lOS Y Ru-106 Y Including: Rh-1 06 Rh-lOS Y Sb-1 27 W Sb-1 29 W Te-127 W Te-127m W Te-1 29 W Te-129m W lncluding:Te-1 29 Te-131m W lncluding:Te-1 31 Te-132 W 1-131 D

ENGINEERING SERVICES I* I' - __ .

CALCUL ATI 10N CUUN INUA I IN SHEET Page _D24 I I(Next 025 -

Project: Nine Mile Point Nuclear Station Unit: -1 Disposition' tŽLA Calculation No. Revision riginator/Date O Reviewer/Date Jo.Metcalf 12/12/06 Appendix E H21C096 0 1-132 D 1-133 0 1-134 D 1-135 D Including;Xe-1 35m Xe-133 Xe-i 33m Xe- 135 Xe-i 35m Xe-138 Cs-134 D Cs-136 D Cs-137 D Including: Ba-1 37m Ba-139 0 Ba-140 0 La-140 W La-141 0 La-142 0 Ce-141 Y Ce-143 Y Ce-144 Y Including: Pr- 144m, Including: Pr-1 44 Pr-143 Y Nd-147 Y Np-239 W Pu-238 Y Pu-239 Y Pu-240 Pu-241 Amn-241 Cm-242 Cm-244 CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC Kr-83m GONADS 1.71 OE-1 85.572E-1 55.855E-1 56.1 60E-1 9-1 .OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 5.050E-1 8 9.498E-1 5 9.980E-1 5 1.050E-1 8-1.OOOE+OO O.OOOE+OO O.OOOE+CO LUNGS 1.640E-1 9 1.266E-1 6 1.331 E-1 6 1.400E-20-1 .OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 3.830E-19 5.617E-16 5.902E-16 6.210E-20-1.OOOE+OO O.OOOE-'-0 .OOOE+OO BONE SUR 2.250E-1 83.437E-1 53.61 2E-1 53.800E-1 9-1 .OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 6.430E-1 9 7.698E-1 68.088E-1 68.51 OE-20-1 .OOOE'-0O OOOOE+O0 0.OOOE+O0 REMAINDER 5.300E-1 9 1.393E-1 5 1.464E-1 5 1.540E-1 9-1,.OOOE+00 O.OOOE+OO O.OOOE+OO EFFECTIVE 1.500E-1 8 3437E-1 53.61 2E-1 53.800E-1 9-1 .OOOE+Oo O.OOOE+OO O.OOOE+OO SKIN(FGR) 3.560E-1 7 1,1 67E-1331.226E-1331.290E-1 7-1 .OOOE+CO O.OGOE+OO O.OOOE+OO Kr-85m GONADS 7.310CE-15 2.594E-1 2 3.653E-1 2 1.570E-1 6-1 .OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 8.41 CE-iS5 2.527E-1 2 3.560E-1 2 1.530E-1 6-1 .CCCE+CC C.CCCE+OC C.CCCE+CC LUNGS 7.040E-1 5 2.379E-1 2 3.351 E-1 2 1.440E-1 6-1 .CCCE+CC C.CCCE+C0 O.CCCE+CC RED MARR 6.43CE-15 2.346E-12 3.3C4E-12 1.42CE-16-1.CCCE+CC C.CCOE+CC O.CCCE+CC BONE SUR 1.88CE-1 45.286E-1 27.446E-1 23.200E-1 6-1 .CCCE+CCC.CCCE+CC C.CCOE+CC

ENGINEERING SERVICES AJLIL III' IdMIIId~~ ~LLI IAr I(Next D2-Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition: 0/,\h Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H210C096 0

Ref, THYROID 7.33CE-1 52.395E-1 23.374E-1 2 1.450E-1 6-i .CCCE+CC C.CCCE+CC C.CCE+CC REMAINDER 6.640E-1552.31 3E-1 2 3.257E-1 2 1.400E-i 6-i .CCE+CC C.CCCE+CC C.CCCE+CC EFFECTIVE 7.480E-15 2.51 1E-12 3.537E-i 21 .520E-16-i .CCCE+CC C.CCE+CC C.CCCE+CC SKIN(FGR) 2.24CE- 4 2.247E-1 13.1 64E-11 11360E-1 5-i .CCCE+CC C.CCCE+CC C.CCE+CC Kr-85 GONADS 1.i7CE-16 8.121E-14 1.704E-12 2.820E-18-1.CCCE+CC C.CCOE+CC C.CCCE+CC BREAST 1.340E-1 67.891 E-14 1.656E-1 22.74CE-1 8-1 .CCCE+CC C.CCCE+CC C.CCCE+C LUNGS 1.140E-16 7.056E-14 i.481E-12 2.45CE-18-1.CCCE+CC C.CCCE+CC C.CCCE+CC RED MARR 1.C9CE-16 6.998E-14 1.469E-12 2.43CE-18-1.COCE+CC C.CCCE+CC C.CCE+CC BONE SUR 2.200E-1 6 1.287E-1 32.7C2E-1 24.470E-1 8-1 .CCCE+CCC.COCOE+CC C.CCE+CC THYROID 1.1 8CE-1 67.459E-1 41 .565E-1 22.59CE-1 8-1 .CCCE+C0OCCCE+CC C.CCCE+CC REMAINDER 1.090E-1 6 6.941 E-1 4 1.457E-1 2 2.41 OE-1 8-1 .CCCE+CC C.CCCE+CC C.CCCE+CC EFFECTIVE 1.1 90E-1 6 7.603E-14 1.596E-1 2 2.640E-1 8-1 .CCCE+CC C.CCCE+CC C.CCCE+CC SKIN(FGR) 1.320E-14 2.304E-1 1 4.835E-10 8.CCCE-16-1.CCOE+CC C.CCCE+CC C.CCCE+CC Kr-87 GONADS 4.OOCE-14 4.962E- 2 5.026E-1 27.61 CE-i 6-1 .OCCE+CC C.COCE+CC C.CCCE+C BREAST 4.500E-1 4 4.740E-1 2 4.802E-1 2 7,270E-1 6-1.CCCE+00 C.CCCE+CC C.CCCE+CC LUNGS 4.040E-1 4 4.603E-1 2 4.663E-1 2 7.060E-1 6-1 .CCCE+CC C.CCCE+CC C.CCCE+CC RED MARR 4.CCCE-14 4.7C8E-12 4.769E-12 7.220E-16-1.CCCE+CO CCCE+CC C.CCCE+CC BONE SUR 6.02OE-14 6.51 4E-1 26.598E-1 29.990E-1 6-i .CCCE+CC .OOCE+CC C.OCCE+CC THYROID 4.1 30E-1 44.473E-1 24.531 E-1 26.86CE-1 6-1 .CCCE+CC C.CCCE+CC 0.CCCE+0 REMAINDER 3.91 CE-i 44.59CE-1 24.65CE-1 27.04CE-1 6-1 .CCCE+CC.COOE+CC C.CCCE+CC EFFECTIVE 4.1 20E-1 44.773E-1 24.835E-1 27.32CE-1 6-1 .OOCE+CC C.OOCE+CC C.CCCE+0C SKIN(FGR) 1.370E-13 8.802E-11 8.916E-11 1.350E-14-1.CCCE+CC C.OCCE+CO 0.OCCE+C Kr-88 GONADS 9.900E-14 2.278E-1 1 2.655E-1 1 1.800E-15-1.CCOE+00 0.CCCE+00 C.COCE+OC BREAST 1.11 CE-i 3 2.1 77E-1 1 2.537E-1 11.720E-1 5-1 .CCCE+CC C.CCCE+00 C.COOE+00 LUNGS 1.01 CE-i 3 2.1 39E-1 1 2.493E-1 1 1.690E-1 5-1 .CCOE+0O 0.00CE+00 C.CCCE+CC RED MARR 1.OOOE-1 3 2.190E-1 1 2.552E-1 1 1.730E-1 5-1.CCCE+00 C.CCCE+00O .CCCE+CC BONE SUR 1.390E-1 3 2.886E-1 1 3.363E-1 1 2.280E-1 5-1.CCOE+00 C.OOCE+00 0.OOCE+00 THYROID 1.030E-1 3 2.01 2E-1 1 2.345E-1 11.590E-1 5-1 .CCOE+00 C.CCCE+CC 0.CCCE+OC REMAINDER 9.790E-14 2.1 39E-1 1 2.493E-1 1 1.690E-1 5-1 .CCCE+00 C.CCCE+0C C.CCCE+CC EFFECTIVE 1.020E-1 3 2.202E-1 1 2.567E-1 1 1.740E-1 5-1 .CCCE+OC C.CCCE+00O .OCCE+00 SKIN(FGR) 1.350E-1 3 5.607E-1 1 6.534E-1 1 4.430E-1 5-1 .CCCE+CC C.COCE+00O .CCOE+00 Rb-86 GONADS 4.71 CE-iS5 2.788E-1 2 5.1 87E-1 1 9.740E-1 7-1 .CCCE+CC 1.340E-09 2.1 50E-09 BREAST 5.340E-1 5 2.662E-1 2 4.953E-11I 9.300E-1 7-1.CCCE'-CC 1.330E-09 2.140E-09 LUNGS 4.71 CE-iS5 2.553E-1 2 4.750E-1 1 8.920E-1 7-1 .CCCE+CC 3.300E-09 2.1 40E-09 RED MARR 4.640E-1 5 2.619E-1 2 4.873E-1 1 9.150E-1 7-1.CCCE+CC 2.32CE-C9 3.72CE-C9 BONE SUR 7,050E-1 5 3.635E-1 2 6.764E-11 11.27CE-1 6-1 .CCCE+CC 4.270E-09 6.860E-09 THYROID 4.840E-1 5 2.599E-1 2 4.836E-1 1 9.080E-1 7-1 .CCCE+CC 1.33CE-C9 2.I40E-09 REMAINDER 4.520E-1 5 2.542E-1 2 4.729E-1 1 8.880E-1 7-1 .CCCE+00 1.380E-09 2.330E-09 EFFECTIVE 4.81 CE-iS5 2.665E-1 2 4.958E-1 1 9.31 CE-i 7-1 .CCCE+CC 1.790E-C9 2.530E-09 SKIN(FGR) 4.85CE-1 42.21 CE-iC4.111 E-C97.72CE-1 5-1 .CCCE+CC C.CCCE+CCC.CCCE+CC Rb-88 GONADS 3.26CE-14 2.788E-12 5.187E-11 9.74CE-17-1.CCCE+CC 1.31CE-12 2.15CE-C9 BREAST 3.67CE-14 2.662E-1 24.953E-1 19.3CCE-1 7-1 .CCCE+CC 1.43CE-1 22.1 4CE-C9 LUNGS 3.31 CE-i 42.553E-1 24.75CE-i118.92CE-1 7-1 .CCCE+CC 1.47CE-10C2.1 4CE-C9

-I

ENGINEERING SERVICES I- At ~ ATrle'%I f'r^KI-r.IIIA-rIIK e%1IEr-r- - ,

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Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition: iALA Calcutation No. Revision EJo.

Originator/Date Metcalf 12/12/06 Reviewer/Date Appendix E H21 0096 0 RED MARR 3.300E-14 2.619E-12 4.873E-1 1 9.150E-17-1.OOGE+OO 1,450E-12 3.720E-09 BONE SUR 4.620E-1 4 3.635E-1 2 6,764E-1 1 1.270E-1 6-1.OOOE+OO 1.470E-1 2 6.860E-09 THYROID 3.370E- 14 2.599E-1 2 4.836E-1 1 9.080E-1 7-1 .OOOE+OO 1.370E-1 2 2.140E-09 REMAI NDER 3.210OE-1 4 2.542E- 12 4.729E-1 18.880E-1 7-1.OOOE+OO 1.380E-1 1 2.330E-09 EFFECTIVE 3.360E-1 4 2.665E- 12 4.958E-1 1 9.31 OE-1 7-1.OOOE+OO 2.260E-1 1 2.530E-09 SKIN(FGR) 1.830E-1 32.21 OE-1 04.111 E-09 7.720E-1 5-1 .OOOE+00 0.OOOE+00 0.0OOE+00 Sr-89 GONADS 7.730E-1 7 7,1 55E-1 4 1.436E-1 2 2.490E-1 8-1 .OOOE+00 7.950E-1 2 8.050E-1 2 BREAST 9.080E-1 7 7.21 2E-1 4 1.447E-1 2 2.51 OE-1 8-1 .OOOE+00 7.960E-1 2 7.980E-1 2 LUNGS 7.080E-17 5.689E-14 1.142E-12 1.980E-18-1.OOOE+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+0O 1.590E-10 1.610E-10 THYROID 7.600E-17 6.063E-14 1,217E-12 2.11OE-18-1.OOOE+00 7.960E-12 7.970E-12 REMAINDER 6.710OE-1 7 5.603E-1 4 1.1 24E-1221.950E-1 8-1 .OOOE+00 3.970E-09 8.250E-09 EFFECTIVE 7.730E-1 7 6.523E-1 4 1.309E-1 2 2.270E-1 8-1 .OOOE+00 1.,760E-09 2.500E-09 SKIN(FGR) 3.690E-1 4 1.91 4E-1 0 3.841 E-09 6.660E-1 5-1 .OOOE+00 0.OOOE+00 0.OOOE+00 Sr-90 GONADS 7.780E-1 8 9.590E-1 5 2.014E-1 3 3.330E-1 9-1 .OOOE+00 2.690E-1 0 5.040E-1 1 BREAST 9.490E-1 8 1.008E-14 2.11 6E-1 33.500E-1 9-1 .OOOE+00 2.690E-1 05.040E-1 1 LUNGS 6.440E-1 8 6307E-1 51 .324E-1 32.1 90E-1 9-1 .OOOE+00 2.860E-06 5.040E-1 1 RED MARR 5.440E-1 85.558E-1 51.1 67E-1 3 1 930E-1 9-1 .000E+00 3.280E-08 6.450E-09 BONE SUR 2,280E-17 2.393E-14 5.025E-13 8.310E-19-1.000E+00 7.090E-08 1.390E-08 THYROID 7.330E-1 87.171 E-1 51 .506E-1 32.490E-1 9-1 .OOOE+00 2.690E-1 05.040E-1 1 REMAINDER 6.11 OE-1 8 6.422E-1 5 1.348E-1 3 2.230E-1 9-1 .OOOE+00 5.730E-09 6.700JE-09 EFFECTIVE 7.530E-1 8 8.1 79E-1 5 1.71 7E-1 3 2.840E-1 9-1 .OOOE+00 6.470E-08 3.230E-09 SKIN(FGR) 9.200E-1 54.032E-1 28.465E-11 11.400E-1 6-1 .OOOE+00 0.OOOE+00 0.000E+00 Sr-91 GONADS 3.380E-1 4 2.1 55E-1 1 5.062E-1 I11.026E-1 5-1 .000E+0O 5.650E-1 1 2.520E-1 0 BREAST 3.830E-1 4 2.059E-1 1 4.838E-1 1 9.806E-1 6-1 .OOOE+00 1.740E-1 1 3.676E-1 1 LUNGS 3,370E-14 1.970E-1 1 4.626E-1 1 9.376E-1 6-1.OOOE+00 2.130E-09 1.055E-1l1 RED MARR 3.310OE-1 4 2.011 E-1 1 4.722E-1 1 9.570E-1 6-1.OOOE+00 2.230E-1 1 5.659E-1 1 BONE SUR 5.200E-14 2.852E-1 1 6.709E-1 1 1.360E-1 5-1 .OOOE+00 1.270E-1 1 2.070E-1 1 THYROID 3.470E-14 2.035E-11 4.782E-11 9.693E-16-1.OOOE+009.640E-12 1.968E-12 REMAINDER 3.240E-14 1.948E-1 14.573E-1 19.268E-1 6-1 .OOOE+00 5.780E-1 02.557E-09 EFFECTIVE 4.929E-1 42.057E-1 14.832E-1 19.793E-1 6-1 .OOOE+00 2.577E-1 08,455E-1 0 SKIN(FGR) 8.1 40E-1 4 1.748E-1 03.987E-1 08.080E-1 5-1 .OOOE+00 0,OOOE+00 0.OOOE+00 Sr-92 GONADS 6.610OE-1 4 1,593E-11I 1.830E-1 1 1.300E-1 5-1 -OOOE+001.020E-1 1 8.180E-1 1 BREAST 7.480E-14 1.520E-1 1 1.745E-1 11.240E-15-1 .OOOE+00 6.490E-12 1.700E-1 1 LUNGS 6.670E-14 1.483E-1 1 1.703E-1 11.210E-15-1.OOOE+00 1.050E-09 7.220E-12 RED MARR 6.620E-14 1.520E-11 1.745E-11 1.240E-15-1.OOOE+00 6.980E-12 2.290E-11 BONE SUR 9.490E-14 2.010OE-1 1 2.308E-11 11.640E-1 5-1 .OOOE+00 4.360E-1 2 8.490E-1 2 THYROID 6.820E-14 1.446E-11 11.661 E-11 11.180E-1 5-1 .OOOE+00 3.920E-1 2 1.300E-1 2 REMAINDER 6.450E-1 4 1.471 E-11 11.689E-11 11200E-1 5-1 .OOOE+00 2.900E-1 0 1.720E-09 EFFECTIVE 6.790E-1 4 1.532E-1 I11.759E-1 1 1.250E-1 5-1 .OOOE+O0 1.700E-1 0 5.430E-1 0 SKIN(FGR) 8.560E-1 4 2.280E-1 1 2.61 8E-11 11.860E-1 5-1,OOOE+00 0.OOOE+00 0.OOOE+00 Y-90 GONADS 1.890E-16 1.586E-13 1.601E-12 5.750E-18-1.OOOE+00 5.170E-13 1.430E-14

[ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D7 (Next 0D28)

Project. Nine Mile Point Nuclear Station Unit: 1- Disposition: WK/~'

Origina~tor/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21CO96 0 BREAST 2.200E-1661.578E-1 3 1.593E-1 2 5.720E-1 8-1 .000E+00 5.1 70E-1331.270E-1 4 LUNGS 1.770E-16 1.313E-13 1.326E-12 4.760E-18-1.000E+00 9.310E-09 1.260E-14 RED MARR 1.620E-16 1.261E-13 1.273E-12 4.570E-18-1000E+00 1.520E-1 I 3.700E-13 BONE SUR 4.440E-16 3.228E-13 3.259E-12 1.170E-17-1.000E+00 1.510E-1 1 3.670E-13 THYROID 1.870E-16 1.385E-13 1.398E-12 5.020E-18-1.000E+00 5.170E-13 1.260E-14 REMAINDER 1.680E-16 1.291E-13 1.303E-124.680E-18-1.000E+00 3.870E-09 9.680E-09 EFFECTIVE 1.900E-16 1.468E-13 1.482E-12 5.320E-18-1000E+00 2.280E-09 2.910E-09 SKIN(FGR) 6.240E-1 4 2.897E-1 0 2.924E-09 1.050E-1 4-1 .000E+00 0.OOOE+00 0.000E+00 Y-91 GONADS 2.560E-16 1.756E-13 3.546E-12 6.1 10E-18-1.000E+0O 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-1 6 1.526E-1 3 3.082E-1 2 5.310OE-1 8-1.000E+00 9.870E-08 2.020E-1 3 RED MARR 2.410E-16 1.521E-13 3.070E-12 5.290E-18-1.000E+O003.190E-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-1 6 1.564E-1 33.1 57E-1 25.440E-1 8-1 .000E+00 8.500E-1 21 .290E-1 3 REMAINDER 2.390E- 16 1.509E-1 3 3.047E-1 2 5.250E-1 8-1 .000E+00 4.200E-09 8.570E-09 EFFECTIVE 2.600E-1661.650E-1 3 3.332E-1 2 5.740E-1 8-1 .000E+00 1.320E-08 2.570E-09 SKIN(FGR) 3,850E-1 4 1.989E-1 0 4.01 6E-09 6,920E-1 5-1 .000E+00 0.000E+00 0.000E+00 Y-92 GONADS 1.270E-14 3.855E-1 2 4.872E-1 2 2.650E-1 6-1 .OOOE+00 2.610OE-1221.960E-1 1 BREAST 1.440E-1 4 3.680E-1 2 4.652E-1 2 2.530E-1 6-1 .OOOE+00 1.500E-1 2 3.550E-1 2 LUNGS 1.270E-1 4 3.535E-1 2 4,468E-1 2 2.430E-1 6-1 .000E+00 1.240E-09 1.390E-1 2 RED MARR 1.250E-14 3.608E-12 4.560E-12 2.480E-16-1.000E+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-1 43.579E-1 24.523E-1 22.460E-1 6-1 .000E+00 1.050E-1 2 1.770E-1 3 REMA INDER 1.220 E-14 3.506 E-12 4.431 E-12 2.410 E-16-1.000E +00 2.030E-1001. 700 E-09 EFFECTIVE 1.300E-1 43.680E-1 24.652E-1 22.530E-1 6-1 ,000E+00 2.11 OE-1 05.1 50E-1 0 SKIN(FGR) 1.1 40E-1 32.022E-1 02.556E-1 0 1.390E-1 4-1 .000E+00 0.000E+00 0.OOOE+00 Y-93 GONADS 4.670E-1 52.1 08E-1 24.989E-1 29.51 OE-1 7-1 .OOOE+00 5.31 OE-1 22.200E-1 1 BREAST 5.300E-1 5 2.026E-1 2 4.794E-1 2 9.140E-1 741.OOE+00 1.740E-1 2 3.130E-1 2 LUNGS 4.680E-1 5 1.937E-1 2 4.585E-1 2 8.740E-1 7-1 .OOOE+00 2.520E-09 8.670E-1 3 RED MARR 4.580E-15 1.972E-12 4.669E-12 8.900E-17-1 .OOOE+00 4.040E-12 4.930E-12 BONE SUR 7.580E-15 2.948E-12 6.977E-12 1.330E-16-1.OOOE+00 3.140E-12 1.730E-12 THYROID 4.790E-15 1.908E-12 4.516E-12 8.610E-17-1 .OOOE+00 9.260E-13 1.260E-13 REMAINDER 4.510OE-1 5 1.91 9E-1 2 4.543E-1 2 8.660E-1 7-1 .OOOE+00 9.250E-1 0 4.090E-09 EFFECTIVE 4.800E-1 5 2.021 E-1 2 4.784E-1 2 9.1 20E-17-1 .OOOE+00 5.820E-1 0 1.230E-09 SKIN(FGR) 8.500E-1 4 2.726E-1 0 6.452E-1 0 1.230E-1 4-1 .OE+00 0.OOOE+00 0.OOOE+00 Zr-95 GONADS 3.530E-14 2.182E-1 1 4.421E-10 7.590E-16-1.000E+00 1.880E-09 8.160E-10 BREAST 4.010OE-14 2.084E-1 1 4.223E-1 0 7.250E-1 6-1.OOOE+00 1.91 OE-09 1.050E-1 0 LUNGS 3.510OE-1 4 1.989E-1 1 4.030E-1 0 6.920E-1 641 .OE+00 2.170E-09 2.340E-1 1 RED MARR 3.430E-14 2.030E-1 1 4.11 2E-1 0 7.060E-1 6-1 .000E+00 1.300E-08 2.1 40E-1 0 BONE SUR 5.620E-14 2.875E-11 5.824E-10 1.000E-15-1.OO01E+00 1.030E-07 4.860E-10 THYROID 3.610OE-14 2.076E-1 1 4.205E-1 0 7.220E-1 6-1 .OOOE+00 1.440E-09 8.270E-1 2 REMAINDER 3.360E-14 1.963E-1 1 3.978E-1 0 6.830E-1 6-1 .OOOE+00 2.280E-09 2.530E-09 EFFECTIVE 3.600E-1 4 2.078E-1 1 4.211 E-1 0 7.230E-1 6-1 .OOOE+00 6.390E-09 1.020E-09 SKIN(FGR) 4.500E-14 2.561E-1 1 5.190E-10 8.910E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D28-(Next -D29 -

Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: rcJm.

Originator/Date Rev'ewer/Date No.

-Calculation Revision J.Metcalf 12/12/06 Apppendix E H21CO96 0 Zr-97 GONADS 8.800E-1 5 2.179E-1 1 7,799E-1 1 9.253E-1 6-1 .000E+00 1.840E-1 0 6.228E-10 BREAST 9.990E-1 5 2.083E-1 1 7.455E-1 1 8.846E-1 6-1 .OOOE+00 4.700E-1 1 8.1 37E-1 1 LUNGS 8.810OE-1 5 1.992E-1 1 7.127E-1 1 8.456E-1 6-1 .OOOE+00 4.1 IOE-09 1.770E-1 1 RED MARR 8.640E-1 5 2.034E-1 1 7.279E-1 1 8.634E-1 6-1.OOOE+00 6.370E-1 1 1.302E-1 0 BONE SUR 1.380E-14 2.881 E-1 1 1.031 E-1 0 1.224E-1 5-1.OOOE+00 3.500E-1 1 4.558E-1 1 THYROID 9.030E-1 5 2.061 E-1 1 7.377E-1 1 8.755E-1 6-1 .000E+00 2.31 OE-1 12.671 E-1 2 REMAINDER 8.480E-1 5 1.966E-1 1 7,035E-1 1 8.345E-1 6-1 .000E+00 2.040E-09 6.990E-09 EFFECTIVE 4.432E-1 42.078E-1 1 7,438E-1 1 8.824E-1 6-1 .000E+00 1.171 E-09 2.283E-09 SKIN(FGR) 5.550E-14 2.281 E-1 08.1 48E-1 0 9587E-1 5-1 .000E+00 0.OOOE+00 0.OOOE+00 Nb-95 GONADS 3.660E-14 2.253E-1 14.435E-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.OOOE+00 4.070E-10 1.070E-10 LUNGS 3.650E-1 4 2.055E-1 1 4.045E-1 0 7.1 60E-1 6-1 .000E+00 8.320E-09 2.740E-1 1 RED MARR 3.560E-14 2.1O1E-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.OOOE+00 5.130E-10 2.940E-10 THYROID 3.750E-1 42.1 44E-1 14.220E-1 07.470E-1 6-1 .OOOE+00 3.580E-1 01.1 80E-1 1 REMAINDER 3.490E-1 4 2.032E-1 1 4.OOOE-1 0 7.080E-1 6-1 .OOOE+00 1.070E-09 1.470E-09 EFFECTIVE 3.740E-14 2.147E-1 1 4.226E-10 7.480E-16-1.OOOE+00 1.570E-09 6.950E-10 SKIN(FGR) 4.300E-1 4 2.598E-1 1 5.11 2E-1 0 9.050E-1 6-1 .OOOE+00 0.OOOE+00 0.OOOE+00 Mo-99 GONADS 7.130E-15 4.282E-12 4.403E-1 1 1.550E-16-1 .000E+00 9.510E-1 1 2.180E-1 0 BREAST 8.130E-1 5 4.1 16E-1 2 4.233E-1 I11.490E-1 6-1.OOOE+00 2.750E-1 1 3.430E-1 1 LUNGS 7.060E-1 5 3.867E-1 2 3.977E-1 1 1.400E-1 6-1.OOOE+00 4.290E-09 1.510OE-1 1 RED MARR 6.820E-1 5 3.923E-1 2 4.034E-1 11.420E-1 6-1 .OOOE+00 5.240E-1 1 8.320E-1 1 BONE SUR 1.240E-1 4 6.105E-1 2 6.278E-1 12.210OE-1 6-1.OOOE+00 4.130E-1 1 6.320E-1 1 THYROID 7.270E-1 5 4.033E-1 2 4.1 47E-1 11.460E-1 6-1 .OOOE+00 1.520E-1 11.030E-1 1 REMAINDER 6.740E-1553.81 2E-1 2 3.920E-11 11.380E-1 6-1 .OOOE+00 1.740E-09 4.280E-09 EFFECTIVE 7.280E-1 5 4.061 E-1 2 4.1 76E-1 11.470E-1 6-1 .OOOE+00 1.070E-09 1.360E-09 SKIN(FGR) 3.1 40E-14 1.039E-1 0 1.068E-09 3,760E-1 5-1 .OOOE+00 0.OOOE+00 0.OOOE+00 Tc-99m GONADS 5.750E-1 5 2.334E-1 2 3.877E-1 2 1.240E-1 6-1 .OOOE+00 2.770E-1 2 9.750E-1 2 BREAST 6.650E-1 5 2.258E-1 2 3.752E-1 2 1.200E-1 6-1.OOOE+00 2.150E-1 2 3.570E-1 2 LUNGS 5.490E-1 5 2.1 27E-1 2 3.533E-1 2 1.1 30E-1 6-1 .OOOE+00 2.280E-1 1 3.140E-1 2 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-1 45.383E-1 28.942E-1 22.860E-1 6-1 .OOOE+00 2.620E-1 24.060E-1 2 THYROID 5.750E-15 2.145E-12 3.564E-12 1.140E-16-1.OOOE+00 5.O1OE-1 18.460E-1 1 REMAINDER 5.150E-15 2.070E-12 3.439E-12 1.100E-16-1.OOOE+00 1.020E-11 3.340E-11 EFFECTIVE 5.890E-15 2.277E-12 3.783E-12 1.210E-16-1.OOOE+00 8.800E-12 1.680E-11 SKIN(FGR) 7.1 40E-1 52.71 OE-1 24.502E-1 2 1.440E-1 6-1 .OOOE+00 0.OOOE+00 0.OOOE+00 Ru-i 03 GONADS 2.191 E-14 1.404E-1 12.783E-10 4.892E-16-1.OOOE+00 3.070E-10 5.720E-10 BREAST 2.512E-14 1.350E-11 2.677E-10 4.705E-16-1.OOOE+00 3.11OE-10 1.200E-10 LUNGS 2.1 80E-1 4 1.273E-1 12.522E-1 04.432E-1 6-1 .OOOE+00 1.561 E-08 7.31 OE-1 1 RED MARR 2.100E-14 1.287E-11 2.551E-104.483E-16-1.OOOE+00 3.190E-10 1.660E-10 BONE SUR 3.892E-14 1.958E-11 3.882E-10 6.823E-16-1.OOOE+00 2.370E-10 9.631E-11 THYROID 2.241E-14 1.331 E-1 12.639E-10 4.638E-16-1 .OOOE+00 2.570E-10 6.250E-1 1 REMAINDER 2.080E-14 1.248E-11 2.472E-104.346E-16-1.OOOE+00 1.250E-09 2.11OE-09

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D29-(Next _D30 Project:- Nine Mile Point Nuclear Station Unit: -1 Disposition.- PJA.p Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21C096 0c Ref.

EFFECTIVE 2.251 E-14 1.332E- 112.641 E-1 0 4.642E-1 6-1.00E+00 2.421 E-09 8.271 E-1 0 SKIN(FGR) 2.774E-1 4 1.785E-1 1 3.543E-1 0 6.229E-1 6-1 .000E+00 0.000E+00 0.000E+00 Ru-lOS GONADS 3.720E-14 1.3 27E- 11 1.861 E-11 8.070 E 1.O000E +00 1.590 E-11 9.670 E-11 BREAST 4.240E- 14 1.271E-1 11 1.783 E- 117.7 30E-16-1. .000E+00 6.610 E-12 1.590 E- 11 LUNGS 3.7 00E- 14 1.210 E-1 11 1.697 E- 117.360E- 16-1. 000OE +00 5.730 E-10 6.210 E-12 RED MARR 3.590E-1 4 1.230E-1 11 1.725E-1 117.480E-1 6-1 ,000E+00 7.700E-1 2 2.350E-1 1 BONE SUR 6.280E-14 1.809E-1 1 2.537E-1 1 1.100E-15-1.000E+00 4.620E-12 8.890E-12 TH YRO ID 3.8 00E- 14 1.260 E-1 11 1.766 E-1 117.660OE- 16-1. .000 E+00 4.150 E-12 1.820E-12 REMAINDER 3.540E-1 4 1.189E-1 1 1.667E-1 1 7.230E-1 6-1.000E+00 1.610OE-1 0 8.540E-1 0 EFFECTIVE 3.810OE-1 4 1.265E-1 11 1.773E-1 1 7.690E-1 6-1 .000E+00 1.230E-1 0 2.870E-1 0 SKIN(FGR) 6.730E-1 47.368E-11 11.033E-1 04.480E-1 5-1 .000E+00 O.0E+00 0.000E+OO Ru-i 06 GONADS 1.010OE-1 4 6.411 E-1 2 1.340E-1 0 2.230E-1 6-1.OOOE+00 1.300E-09 1.640E-09 BREAST 1.1 60E-1 4 6.1 52E-1 2 1.286E-1 0 2.1 40E-1 6-1 .000E+00 1.780E-09 1.440E-09 LUNGS 1.01 0E-1 4 5.836E-1 2 1.220E-1 0 2.030E-1 6-1 .000E+00 1.040E-06 1.420E-09 RED MARR 9.750E-15 5.893E-12 1.232E-10 2.050E-16-1.000E+00 1.760E-09 1.460E-09 BONE SUR 1.720E-14 8.883E-12 1.856E-10 3.090E-16-1.000E+00 1.610E-09 1.430E-09 THYROID 1.030E-14 6.066E-12 1.268E-10 2.110E-16-1.000E+00 1.720E-09 1.410E-09 REMAINDER 9.630E-15 5.721E-12 1.196E-10 1.990E-16-1.000E+00 1.200E-08 2.110E-08 EFFECTIVE 1.040E-1 4 6.095E-1 2 1.274E-1 0 2.1 20E-1 6-1 .000E+00 1.290E-07 7.400E-09 SKIN(FGR) 1.090E-13 4.082E-10 8.531E-09 1.420E-14-1.000E+00 0.000E+00 0.OOOE+00 Rh-lOS GONADS 3.640E-1 52.127E-1 21.41 1E-1 17.960E-17-1 .OOOE+OO 2.110E-i115.800E-1 1 BREAST 4.160E-1S 2.063E-12 1.369E-11 7.740E-17-1.OOOE+0O 5.610E-12 8.970E-12 LUNGS 3.570E-15 1,935E-12 1.284E-11 7.260E-17-1.OOOE+OO 9.580E-10 3.860E-12 RED MARR 3.380E-1 51 .946E-1 21.291 E-1 17.300E-1 7-1 .000E+00 7.770E-1 21 .470E-1 1 BONE SUR 7.530E-15 3.332E-12 2.210E-1 I 1.250E-16-1.OOOE+00 4.460E-12 6.750E-12 THYROID 3.680E-15 1.983E-12 1.316E-11 7.440E-17-1.OOOE+OO 2.880E-12 2.910E-12 REMAINDER 3.390E-1 5 1.885E-1 2 1.250E-1 1 7.070E-1 7-1.OOOE+0O 4.530E-1O0 1.270E-09 EFFECTIVE 3.720E-15 2.031E-12 1.347E-11 7,620E-17-1.OOOE+OO 2.580E-10 3.990E-10 SKIN(FGR) 1.070E-1 4 4.691 E-1 2 3.11 2E-1 11.760E-1 6-1 .OOOE+OO O.000E+OO 0.OOOE+0O Sb-127 GONADS 3.260E-1 4 1.985E- 11 2.441 E-10 7.1 OOE-1 6-1.000E+0O 2.520E-1 0 6.140E- 10 BREAST 3.720E-1 4 1.904E-1 1 2.341 E-1 0 6.810OE-1 6-1.OOOE+O0 9.120E-1 1 7.600E-1 1 LUNGS 3.240E-1 4 1.809E-1 1 2.224E- 10 6.470E-1 6-1 .OOOE+O0 6.940E-09 1.570E-1 1 RED MARR 3.140E-1 4 1.834E- 11 2.255E-1 0 6.560E-1 6-1.OOOE+0O 1.610OE-1O0 1.330E-1 0 BON E SUR 5.520E-1 4 2.720E- 11 3.345E-1O0 9.730E- 16-1.OOOE+0O 1.340E-1O0 5.240E-1 1 THYROID 3.330E-1 4 1.884E-1 112.31 7E-1 0 6.740E-1 6-1 .000E+OO 6.1 50E-1 1 4.640E-1 2 REMAIN DER 3.090E-1 4 1.,775E-1 1 2.1 83E-1 0 6.350E-1 6-1 OOOE+00 2.330E-09 5.870E-09 EFFECTIVE 3.330E-1 4 1.890E-1 112.324E-1 0 6.760E-1 6-1 .OOOE+00 1.630E-09 1.950E-09 SKIN(FGR) 5.580E-14 7.967E-1 1 9.799E-10 2.850E-15-1.OOOE+O0 O.OOOE+00 0.OOOE+OO Sb-129 GONADS 6.970E-14 2.336E-1i1 3.231E-1i1i.440E-15-1.OOOE+OO 2.150E-1i1i.510E-10 BREAST 7.910E-14 2.222E-1 1 3.074E-1 1 1.370E-1S-1.OOOE+OO 1,280E-1 1 2.560E-1 1 LUNGS 6.980E-14 2.141E-1i 2.962E-11 1.320E-1S-1.OOOE+OO 8.980E-1O 9.390E-12 RED MARR 6.860E-142.190E-11 3.029E-11 1.360E-15-1.OOOE+00 1.700E-11 3.670E-11 BONE SUR 1.070E-13 3.033E-11 4.196E-11 1,870E-15-1.OOOE+OO 1.460E-ii 1.340E-11

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Project. Nine Mile Point Nuclear Station Unit: 1I Disposition: WIA Calculation No. Revision riginator/Date O Reviewer/Date J., Metcalf 12/12/06 Appendix E H21C096 0j THYROID 7.160E-14 2.174E-1 1 3.007E-1 1 1.340E-15-1.000E+00 9.720E-12 1.470E-12 REMAINDER 6.710E-14 2.125E-11 2.939E-11 1.310E-15-1.000E+00 1.870E-10 1.450E-09 EFFECTIVE 7.140E-14 2.238E-11 3.096E-11 1.380E-15-1.OOOE+00 1.740E-10 4.840E-10 SKIN(FGR) 1.050E-13 8.273E-1 1 1.144E-10 5.100E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 Te-1 27 GONADS 2.370E-16 1.191E-13 2.661E-13 5.480E-18-1.000E+00 2.020E-12 4.020E-12 BREAST 2.7302-16 1.158E-13 2.588E-13 5.330E-18-1.000E+00 1.880E-12 3.0002-12 LUNGS 2.320E-1 6 1.0602-1 3 2.370E-1 34.880E-1 8-1.0002+00 4.270E-1 0 2.890E-1 2 RED MARR 2.210E-16 1.0582-13 2.3652-13 4.870E-18-1.OOOE+00 4.0902-12 6.5702-12 BONE SUR 4.650E-16 1.862E-1 34.162E-13 8.5702-18-1 .OOOE+00 4.090E-12 6.4602-12 THYROID 2.4002-16 1.1 06E-1 32.472E-1 35.090E-1 8-1 .OOOE+00 1.8402-12 2.8602-12 REMAINDER 2.2102-16 1.0362-13 2.316E-13 4.770E-18-1 .0002+00 1.1102-10 6.1302-10 EFFECTIVE 2.4202-1 6 1.1252-1 3 2.51& 3E- 35.1802-1 8-1 ,OOOE+00 8.600E-11I 1.8702-1 0 SKIN(FGR) 1.1402-1 4 1.1732-1 1 2.622E-1 1 5.4002-1 6-1 .OOOE+00 0.000E+00 0.OOOE+00 Te-1 27m GONADS 1.9002-1 6 4.6892-1 3 9.6422-1 2 1.6302-1 7-1.0002+00 1.1002-1 0 1.2502-1 0 BREAST 2.690E-1 6 5,150E-1 3 1.059E-1 1 1.790E-1 7-1.0002+00 1.1002-1 0 9.7402-1 1 LUNGS 7.6202-1 7 1.602E-1 3 3.295E-1 2 5.5702-1 8-1.0002+00 3.340E-08 9.6202-1 1 RED MARR 6.4302-17 1.2492-13 2.5672-12 4.3402-18-1.0002+00 5.3602-09 5.4302-09 BONE SUR 3.9402-16 9.0052-131.8522-113.1302-17-1.0002+00 2.0402-08 2.0702-08 THYROID 1.5002-16 2.7792-13 5.7142-12 9.6602-18-1.0002+00 9.6602-11 9.4302-11 REMAINDER 8.640E-17 1.9992-13 4.1112E-12 6.9502-18-1.0002+00 1.6602-09 2.9802-09 EFFECTIVE 1.4702-16 3.2512-13 6.6842-12 1.1302-17-1.0002+00 5.8102-09 2.2302-09 SKIN(FGR) 8.4902-1 6 1.4962-1 2 3.0762-1 15.2002-1 7-1.0002+00 0.0002+00 0.0002+00 Te- 129 GONADS 2.7102E-S5 3.8892-1 3 3.9222-1 3 6.51 OE-1 7-1.000E+00 5.050E-1 3 1.590E-1 2 BREAST 3.1202-1 5 3.8002-1 3 3.8322-1 36.3602-1 7-1.0002+00 5.3902-1 36.0502-1 3 LUNGS 2.6402-iS5 3.2982-1 3 3.3262-1 3 5.520E-1 7-1 000E+00 1.530E- 10 4.9102E-1 3 RED MARR 2.5402-iS 3.2982-13 3.3262-13 5.S202-17-1.0002+00 6.1902-13 7.6402-13 BONE SUR 4.8802-15 5.7532-13 S.8022-139.6302-17-1.0002+00 6.2202-135.4002-13 THYROID 2.7402-iS 3.525E-13 3.5552-13 5.900E-17-1.0002+00 S.0902-13 3.3602-13 REMAINDER 2.520E-iS 3.2622-13 3.2892-13 5.4602-17-1.0002+00 7.2802-12 1.7902-10 EFFECTIVE 2.750E-IS 3.5902-13 3.6212-13 6.0102-17-1.0002+00 2.0902-1 1 5.4502-1 1 SKIN(FGR) 3.570E-1 4 3.4292-1 1 3.458E-1 15.740E-1 5-1.0002+00 0.0002+00 0.0002+00 Te-1 29m GONADS 1.560E-15 2.2062-12 4.7992-1 1 8.5612-17-1.0002+00 1.7802-10 2.4202-10 BREAST 1.810E-15 2.181E-12 4.7392-1 1 8.4S4E-17-1.0002+00 1.690E-10 1.664E-10 LUNGS 1.4602-1 51.7412E-1 2 3.8152-11I 6.8082-1 7-1.0002+00 4.0302-08 1.5932-1 0 RED MARR 1.4202-15 1.7292-12 3.7932-11 6.7682-17-1.0002+00 3.1002-09 3.5002-09 BONE SUR 2.600E-iS5 3.287E-1 2 7.1472-1 1 1.275E-1 6-1.0002+00 7.050E-09 7.9902-09 THYROID 1.5602-1 5 1.9232-1 24.2012E-1 17.4952-1 7-1.0002+00 1.5602-1 0 1.5722-1 0 REMAINDER 1,410E-iS5 1.7462-1 2 3.8222-1 1 6.8192-1 7-1.0002+00 3.2702-09 7.1962-09 EFFECTIVE 3.3372-1 5 1.9742-1 24.3082-1 1 7.6862-1 7-1.0002+00 6.4842-09 2.9252-09 SKIN(FGR) 1.4902-14 1.5012-10 3.3602-09 6.0012-15-1.0002+00 0.0002+00 0.0002+00 Te-131m GONADS 6.8502-144.0202-11 2.3432-10 1.5352-15-1.000E+00 2.3402-10 7.415E-10 BREAST 7.7802-14 3.8532-11 2.2462-10 1,4722-15-1.0002+00 9.250E-11 1.3612-10 LUNGS 6.8302-14 3.6S72-11 2.1312-10 1.3972-15-1.0002+00 2.2302-09 6.33S2-11

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Project:- Nine Mile Point Nuclear Station Unit: 1 Disposition: 01LA, Oriinto/DteReviewer/Date Calculation No. Revision J.Mtcl 2/12/06 Appendix E H21 C096 0 Ref.

RED MARR 6.680E-1 4 3.736E-1 1 2.178E-1 0 1.427E-1 5-1.OOOE+00 1.410OE-1 0 2.435E-1 0 BONE SUR 1.090E-13 5.467E-1 1 3.189E-10 2.090E-15-1.000E+00 2.270E-10 3.248E-10 THYROID 7.020E-14 3.741E-1 1 2.181E-10 1.429E-15-1.000E+00 3.610E-08 4.383E-08 REMAINDER 6.550E-14 3.626E-1 1 2.1 13E-10 1.385E-15-1.000E+00 9.460E-10 3.153E-09 EFFECTIVE 7.463E-1 4 3.825E-1 1 2.229E-1 0 1.461 E-1 5-1.000E+00 1.758E-09 2.51 4E-09 SKIN(FGR) 8.850E-14 1.033E-1006.1 88E-1 0 4,056E-1 5-1 .000E+00 0.000E+00 0000OE+00 Te-132 GONADS 1.020E-14 6.812E-1 2 7.706E-1 1 2.450E-16-1 .000E+00 4.150E-10 5.410E-10 BREAST 1.1 80E-1 4 6.756E-1 2 7.643E-1 1 2.430E-1 6-1 .000E+00 3,630E-1 0 3.500E-1 0 LUNGS 9.650E-15 5.727E-12 6.479E-1 1 2.060E-16-1.000E+00 1.670E-09 3.300E-10 RED MARR 8.950E-15 5.588E-12 6.322E-1 1 2.010E-16-1.000E+00 4.270E-10 4.440E-10 BONE SUR 2.420E-14 1.273E-11 11.441 E-10 4.580E-16-1 .000E+00 7.120E-10 8.300E-10 THYROID 1.020E-1 45.978E-1 2 6762E-1 12.1 50E-1 6-1 .000E+00 6.280E-08 5.950E-08 REMAINDER 9.1 60E-1 55.644E-1 26.385E-1 12.030E-1 6-1 .000E+00 7.890E-1 0 1.490E-09 EFFECTIVE 1.030E-1 4 6.339E-1 2 7.171 E-1 1 2.280E-1 6-1 .000E+00 2.550E-09 2.540E-09 SKIN(FGR) 1.390E-1 4 8.31 3E-1 2 9.405E-1 1 2.990E-1 6-1 .000E+00 0.000E+00 0000OE+00 1-13 1 GONADS 1.780E-14 1,119E-1 1 1.789E-1 0 3.940E-1 6-1.000E+00 2.530E-1 1 4,070E-1 1 BREAST 2.040E-14 1.082E-1 1 1.730E-1 0 3,810OE-1 6-1.000E+00 7.880E-1 1 1.210OE-1 0 LUNGS 1.760E-14 1.016E-1 1 1.626E-10 3.580E-16-1.000E+00 6.570E-10 1.020E-10 RED MARR 1.680E-1 4 1.022E-1 1 1.635E-1 0 3.600E-1 6-1.OOOE+00 6.260E-1 1 9,440E-1 1 BONE SUR 3.450E-1 4 1.675E-1 1 2.679E-1 0 5.900E-1 6-1 .OOOE+00 5.730E-1 1 8.720E-1 1 THYROID 1.810E-14 1.053E-1 11.685E-10 3.710E-16-1 .000E+00 2.920E-07 4.760E-07 REMAINDER 1.670E-14 9,908E-1 2 1.585E-1 0 3.490E-1 6-1.000E+00 8.030E-1 1 1.570E-1 0 EFFECTIVE 1.820E-14 1.067E-1 11.707E-1 0 3.760E-1 6-1 .OOOE+00 8.890E-09 1.440E-08 SKIN(FGR) 2.980E-1 4 1.825E-1 1 2.920E-1 0 6.430E-1 6-1.000E+00 0.00011+00 0.OOOE+00 1-132 GONADS 1.090E-1 3 2,523E-1 1 2.771 E-1 1 2.320E-1 5-1 .OOOE+00 9.950E-1 2 2.330E-1 1 BREAST 1.240E-1 3 2.414E-1 1 2.652E-1 1 2.220E-1 5-1.OOOE+00 1.410OE-1 1 2.520E-1 1 LUNGS 1.090E-1 3 2.305E-1 1 2.532E-1 1 2.120E-1 5-1 .00E.+00 2.710OE-1 0 2.640E-1 1 RED MARR 1.070E-1 3 2.360E-1 1 2.592E-1 1 2.170E-1 5-1.OOOE+00 1.400E-1 1 2.460E-1 I BONE SUR 1.730E-1 3 3.327E-1 1 3.655E-1 1 3.060E-1 5-1.OOOE+00 1.240E-1 1 2.190E-1 1 THYROID 1.1 20E-1 3 2.381 E-1 1 2.61 6E-1 1 2.1 90E-1 5-1 .OOOE+00 1,.740E-09 3.870E-09 REMAINDER 1.050E-1 3 2.283E-1 1 2.509E-1 1 2,100E-1 5-1 .OOOE+00 3.780E-1 1 1.650E-1 0 EFFECTIVE 1.120E-1 3 2.403E-1 1 2.640E-1 1 2.21 OE-1 5-1 .OOOE+00 1.030E-1 0 1.820E-1 0 SKIN(FGR) 1.580E-1 3 8.1 99E-1 1 9.007E-1 1 7.540E-1 5-1 .OOOE+00 0.OOOE+00 0.000E+00 1-133 GONADS 2.870E-1 4 1.585E-1 1 6.748E-1 1 6.270E-1 6-1 .OOOE+00 1.950E-1 1 3.630E-1 1 BREAST 3.280E-14 1.519E-1 1 6.468E-1 16.01 OE-1 6-1.OOOE+00 2.940E-11I 4.680E-1 1 LUNGS 2.860E-1 4 1.446E-1 1 6,156E-1 1 5,720E-1 6-1 .OOOE+00 8.200E-1 0 4.530E-1 1 RED MARR 2.770E-1 4 1.466E-1 1 6.242E-1 1 5.800E-1 6-1 .000E+00 2.720E-1 1 4.300E-1 1 BONE SUR 4.870E-1 4 2.161 E-1 1 9.202E-1 1 8.550E-1 6-1.OOOE+00 2.520E-1 1 4.070E-1 1 THYROID 2.930E-1 4 1.502E-1 1 6.393E-1 1 5.940E-1 6-1 .OOOE+00 4.860E-08 9.1 OOE-08 REMAINDER 2.730E-1 4 1.418E-1 1 6.038E-1 1 5.610OE-1 6-1.OOOE+00 5.OOOE-1 1 1.550E-1 0 EFFECTIVE 2.940E-1 4 1.509E-1 1 6.425E-1 1 5.970E-1 6-1 .OOOE+00 1.580E-09 2.800E-09 SKIN(FGR) 5.830E-1 4 1.1 50E-1 0 4.897E-1 0 4.550E-1 5-1 .OOOE+00 0.OOOE+00 0.OOOE+00 1-134 GONADS 1.270E-13 1.200E-1 1 1.202E-1 1 2.640E-15-1 .OOOE+00 4.250E-1 2 1.100E-1 1

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Project: Nine Mile Point Nuclear Station Unit: -I Disposition: iJ/A Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21C096 0 Ref.

BREAST 1.440E-1 3 1.145E-1 1 1.147E-1 1 2.520E-1 5-1.OOOE+00 6.170E-1 2 1.170E-1 1 LUNGS 1.270E-13 1.10E-ill1.102E-1 1 2.420E-15-1 .OOCE+00 1.430E-10 1.260E-1 1 RED MARR 1.250E-13 1.1 27E-11 11.129E-1 1 2.480E-15-1 .OCOE+0O 6.080E-12 1.090E-1 1 BONE SUR 1.960E-13 1.568E-11 11.571 E-1 1 3.450E-15-1 .OOCE+0O 5.310E-1 2 9.320E-12 THYROID 1.300E-13 1.127E-11 11.1 29E-1 1 2.48CE-15-1 .OOOE+CO 2.880E-10 6.210E-10 REMAINDER 1.220E-13 1.091 E-11 11.093E-1 1 2.400E-1 5-1 .OCCE+00 2.270E-11 11.340E-10C EFFECTIVE 1.300E-13 1.1 50E-11 11.152E-1 1 2.530E-15-1 .OOOE+00 3.550E-1 1 6,660E-1 1 SKIN(FGR) 1.870E-1 3 4.477E-1 1 4.485E-1 1 9.850E-1 5-1 .COOE+00 0.OOOE+00O0.OOOE+00 1-135 GONADS 8.07SE-14 3.1 13E-i 1 5.489E-11 11.599E-15-i .00OE+CO 1.700E-1 1 3.610E-i11 BREAST 9.1 43E-1 4 2.971 E-1 1 5.240E-i11 1.526E-i 5-1 .OOOE+00 2.340E-1 1 3.850E-i11 LUNGS 8.1 45E-1 4 2.886E-1 1 5.089E-1 I11.482E-1 5-1 .OOCE+00 4.410CE-i10 3.750E-1 1 RED MARR 8.054E-14 2.965E-1 1 5.228E-1 1 1.523E-i 5-i .OOOE+00 2.240E-1 1 3.650E-1 1 BONE SUR 1.184E-13 3.983E-1 I 7,024E-1 1 2.046E-15-1.OCOE+00 2.010E-1i1 3.360E-1i1 THYROID 8.324E-1 4 2.852E-1 1 5.030E-1 I11.465E-1 5-1 .OOOE+00 8.460E-09 1.790E-08 REMAINDER 7.861 E-1 4 2.883E-1i1 5.084E-1 11.481 E-1 5-1.COOE+00 4.700E-1 1 1.540E-1i0 EFFECTIVE 8.294E-14 2.989E-1 1 5.271 E-11 11.535E-1 5-1 .OOOE+00 3.320E-1 06.OBOE-1O SKIN(FGR) 1.156E-1 3 9.826E-1 1 1.733E-1 0 5.047E-1 5-1.OOOE+00 0.OOOE+O0 0.OOOE+CO Xe- 133 GONADS 1.61 CE-i 5 1.465E-1 2 2.052E-1 115.200E-1 7-1 .OOCE+00 0.OOOE+00 0.OOOE+00 BREAST 1.960E-1 5 1.505E-1 2 2.1 07E-1 1 5.340E-1 7-1 .OOOE+00 0.COOE+00 0.OOOE+00 LUNGS 1.320E-1 5 1.045E-1 2 1.464E-1 1 3.71 CE-i 7-1 .OOOE+00 0.COOE+O0 0.OCOE+00 RED MARR 1.070E-1 5 8.791 E-13 1.231 E-1 1 3.120E- 17-1.OOOE+00 0.COOE+00 0.OOOE+00 BONE SUR 5.1 30E-15S 4.254E-1 2 5.958E-11 1.51 CE-i 6-1 .COOE+00 0.OOOE+00 0.OOOE+00 THYROID 1.51 CE-iS 1.181 E-1 2 1.653E-1 14.1 90E-1 7-1 .OOCE+00 0.OOOE+0O 0.000E+00 REMAINDER 1.240E-1 5 1.042E-1 2 1.460E-1 1 3.700E-1 7-1 .OOOE+C0O0.OOOE+00 0.OOOE+00 EFFECTIVE 1.560E-1 5 1.299E-1 2 1.819E-1 14.61 OE-1 7-i.OOOE+00 0.OOCE+00 0.OOOE+00 SKIN(FGR) 4.970E-1 5 1.953E-1 2 2.734E-11I 6.930E-1 7-1.OOOE+00 O.OOCE+00 0.OOOE+0O Xe-i 33m GONADS 1.61 CE-i 5 1.465E-1 2 2.052E-1 1 5.200E-1 7-1 .OOOE+00O .OOOE+00 0.OOOE+00 BREAST 1,960E-1 5 1.505E-1 2 2.107E-1i1 5.340E-1 7-1.OOOE+0C 0.OOOE+00O .OOOE+00 LUNGS 1.320E-1 5 1.045E-1 2 1,.464E-1 13.71 CE-i 7-1 .OOOE+00 0.OCOE+00 0.OOOE+00 RED MARR 1.070E-1 5 8.79i E-1 3 1.231 E-1 1 3.i20E-1 7-1.OOOE+00 0.OOOE+00 0.OOOE+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 i.510E-16-i.OOOE+00O .OOOE+00 0.OOOE+00 THYROID 1.51 CE-i 51.181 E-1 2 1.653E-i114.1 90E-1 7-1 .OOOE+0O 0.OOOE+00 0.00OE+00 REMAINDER 1.240E-1 51 .042E-i 2 1.460E-i113.700E-i 7-1 .OOOE+00 0.OOOE+00 O.OOOE+00 EFFECTIVE 1.370E- 5 1.299E-i 21.81 9E-i114.61 CE-i 7-1 .OOCE+00 0.OOOE+00 0.OOCE+00 SKIN(FGR) 4.970E-1 5 1.953E-i 2 2.734E-1 1 6.930E-1 7-i .CCCE+CC C.CCCE+CC C.OCCE+CC Xe-i 35 GONADS 1.170E-1 4 5.455E-1 2 1.194E-1 1 2.530E-1 6-i .COCE+CC C.COCE+CC C.CCCE+CC BREAST 1.330E-1 4 5.325E-i 2 1.1 66E-1 1 2.470E-1 6-1 .CCCE+CC C.COCE+CC C.CCCE+CC LUNGS 1.i 30E-1 4 4.959E-1 2 1.086E-1 1 2.300E-1 6-i .CCCE+C0OC.CCOE+CC C.CCCE+0C RED MARR 1.070E-i4 4.959E-1 2 1.086E-1i1 2.300E-1 6-i.CCOE+C0OC.COCE+00OC.OCCE+0C BONE SUR 2.570E-14 9.120E-1 2 1.997E-1i1 4.230E-1 6-i.CCCE+CC C.CCCE+CC C.CCOE+CC THYROID 1.180E-1 4 5.023E-1 2 1.1 CCE-i I 2.330E-1 6-i .CCCE+CC C.CCCE+CC C.CCCE+CC REMAINDER 1.080E-14 4.829E-1 2 1.058E-1 1 2.24CE-16-1 .COCE+C0OC.CCCE+CC C.OCOE+CC EFFECTIVE 1.190E-14 5.21 7E-1 2 1.1 42E-1 1 2.420E-1 6-i .CCCE+0C C.CCCE+CC C.CCCE+CC SKIN(FGR) 3.1 20E-14 4.506E-1 1 9.867E-1 1 2.090E-1 5-i .COCE+CC C.CCCE+CC C.CCCE+CC

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition- O)A Originator/Date Reviewer/Date Calculation No. Reiso J.Metcalf 12/12/06 Appendix E H21 C096 0 Xe-i 35m GONADS 2.000E-1 4 5,933E-1 3 5.933E-1 3 4.480E-i 6-i .000E+00 0.000E+00 0.OOOE+00 BREAST 2.290E-1 4 5.695E-1 3 5.695E-1 3 4.300E-1 6-1.000E+00 0.000E+00 0.000E+00 LUNGS 1.980E-1 4 5.351 E-1 3 5.351 E-1 3 4.040E-1 6-1.000E+00 0.000E+00 0.000E+00 RED MARR 1.910E-14 5.404E-13 5.404E-13 4.080E-16-1.000E+00 0.000E+00 0.000E+00 BONE SUR 3.500E-14 8.251E-13 8.251E-13 6.230E-16-i,000E+00 0.000E+00 0.000E+00 THYROID 2.040E- 4 5.61 SE-i 35.61 SE-i 34.240E-1 6-1 .000E+00 0.000E+00 0.000E+00 REMAINDER 1.890E-1 45.245E-1 35.245E-1 33.960E-1 6-1 .000E+00 0.000E+00 0.000E+00 EFFECTIVE 2.040E-1 4 5.61 5E-1 3 5.61 5E-1 3 4.240E-i 6-1 .000E+00 0.000E+00 O.000E+00 SKIN(FGR) 2.970E-1 4 1.867E-1221.867E-1 2 1.41 0E-1 5-1 .000E+00 0.000E+00 0.000E+00 Xe-i 36 GONADS 5.590E-14 1.315E-1 2 1.315E-1 2 1.070E-1 5-1.000E+00 0.000E+00 0.000E+00 BREAST 6.320E-1 4 1.254E-1 2 1.254E-1 2 1.020E-1 5-1 .000E+00 0.000E+00 0.OOOE+00 LUNGS 5.660E-1 4 1.225E-1221.225E-1 2 9.970E-1 6-1 .000E+00 0.OOOE+00 0.000E+00 RED MARR 5.600E-14 1.254E-12 1.254E-12 1.020E-15-1.OOOE+00 0.000E+00 0.OOOE+00 BONE SUR 8.460E-1 4 1.733E-1 2 1.733E-1 21.41 OE-1 5-1 .000E+00 0.000E+00 0.000E+00 THYROID 5.770E-1 41.1 74E-1 21.1 74E-1 29.550E-1 6-1 .000E+00 0.000E+00 0.000E+00 REMAINDER 5.490E-14 1.222E-1 2 1.222E-1 2 9.940E-1 6-i .000E+00 0.000E+00 0.000E+00 EFFECTIVE 5.770E-14 1.266E-1 2 1.266E-1221.030E-1 5-1 .000E+00 0.000E+00 0.000E+00 SKIN(FGR) 1.070E-1 3 9.403E-1 2 9.403E-1 2 7.650E-1 5-1 .000E+00 0.OOOE+00 0.000E+00 Cs- 134 GONADS 7.400E-1 4 4.607E-1 1 9.646E-1 0 1.600E-1 5-1 .000E+00 1.300E-08 2.060E-08 BREAST 8.430E-1 4 4.406E-1 1 9.224E-1 0 1.530E-1 5-1 .OOOE+00 1.080E-08 1.720E-08 LUNGS 7.370E-14 4.204E-11 8.802E-10 1.460E-15-1.000E+00 1.180E-08 1.760E-08 RED MARR 7.1 90E-1 4 4.262E-1 1 8.922E-1 0 1.480E-1 5-1 .000E+00 1.1 80E-08 1.870E-08 BONE SUR 1.200E-1 3 6.1 05E-1 I11.278E-09 2.1 20E-1 5-1 .000E+00 1.100OE-08 1.740E-08 THYROID 7.570E-14 4.377E-1119.1 63E-1 0 1.520E-1 5-1 .000E+00 1.110OE-08 1.760E-08 REMAINDER 7.060E-1 4 4.147E-1 1 8.681 E-1 0 1.440E-1 5-1 .000E+00 1.390E-08 2.21 0E-08 EFFECTIVE 7.570E-14 4.377E-1 19.1 63E-1 0 1.520E-1 5-1 .000E+00 1.250E-08 1.980E-08 SKIN(FGR) 9.450E-14 6.249E-1 1 1,308E-09 2.170E-15-1.000E+00 0.000E+00 0.000OE+00 Cs-136 GONADS 1.040E-1 3 6.223E-1 1 1.1 02E-09 2.1 80E-1 5-1 .000E+00 1.880E-09 3.040E-09 BREAST 1.180E-1 3 5.966E-1 1 1,056E-09 2.090E-1 5-1.000E+00 1.670E-09 2.650E-09 LUNGS 1.040E-1 3 5.71 0E-1 1 1.011 E-09 2.000E-1 5-1 .000E+00 2.320E-09 2.620E-09 RED MARR 1.010E-13 5.824E-11 1.031E-09 2.040E-15-1.OOOE+00 1.860E-09 2.950E-09 BONE SUR 1.660E-1 3 8.422E-11 11.491 E-09 2.950E-1 5-1 .OOOE+00 1.700E-09 2.710OE-09 THYROID 1.070E-1 3 5.852E-1 1 1.036E-09 2.050E-1 5-1 .000E+00 1.730E-09 2.740E-09 REMAINDER 9.950E-1 4 5.652E-1 11.001 E-09 1.980E-1 5-1 .OOOE+00 2.1 90E-09 3.520E-09 EFFECTIVE 1.060E-1 3 5.966E-1 11.056E-09 2.090E-1 5-1 .OOOE+00 1.980E-09 3.040E-09 SKIN(FGR) 1.250E-1 3 7.251 E-1 11.284E-09 2.540E-1 5-1 .000E+00 0.000E+00 0.0OOE+00 Cs-137 GONADS 2.669E-14 1.669E-1 1 3.530E-10 5.840E-1 6-1.OOOE+00 8.760E-09 1.390E-08 BREAST 3.047E-14 1.596E-1 1 3.376E-1 0 5.585E-1 6-1 .000E+00 7.840E-09 1.240E-08 LUNGS 2.649E-1 4 1.51 7E-1 1 3.209E-1 0 5.309E-1 6-1 .000E+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-1 1 4.734E-10 7,832E-16-1.OOOE+00 7.940E-09 1.260E-08 THYROID 2.725E-1 4 1.588E-1 1 3.358E-1 0 5.556E-1 6-1 .OOOE+00 7.930E-09 1.260E-08 REMAINDER 2.536E-1 4 1.490E-1 13.1 52E-1 0 5.21 SE-i 6-i.OOOE+00 9.1 20E-09 1.450E-08

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Project. Nine Mile Point Nuclear Station Unit.- -1 Disposition: i..Ii Originator/Date Reviewer/Date Clulation No. Revision J.Metcalf 12/12/06 Appendix E H1 C096 0 EFFECTIVE 2.725E-1 4 1.585E-1 1 3.353E-1 0 5.546E-1 6-1 .000E+00 8.630E-09 1,350E-08 SKIN(FGR) 4.392E-1 45.253E-11 11.11 OE-09 1.836E-1 5-1 .000E+00 0.000E+00 0.000E+00 Ba-139 GONADS 2.130E-15 3.368E-13 3.429E-134.790E-17-1.000E+00 2.560E-12 1.560E-12 BREAST 2.450E-1 5 3.297E-1 3 3.357E-1 3 4.690E-1 7-1 .000E+00 2.460E-1 2 5.1 70E-1 3 LUNGS 2.030E-1 5 3.002E-1 3 3.057E-1 3 4.270E-1 7-1 .000E+00 2.530E-1 0 3.890E-1 3 RED MARR 1.870E-15 2.932E-13 2.985E-13 4.170E-17-1.000E+00 3.410E-12 8.590E-13 BONE SUR 5.290E-15 6.841E-13 6.965E-13 9.730E-17-1.000E+00 2.490E-12 4.380E-13 THYROID 2.130E-15 3.044E-13 3.100E-13 4.330E-17-1.000E+00 2.400E-12 2.660E-13 REMAINDER 1,.920E-1 5 2.932E-1 3 2.985E-1 3 4.1 70E-1 7-1 .000E+00 4.820E-1 1 3.570E-1 0 EFFECTIVE 2.170E-15 3.227E-13 3.286E-13 4.590E-17-1,OOOE+O0 4.640E-1 1 1.080E-10 SKIN(FGR) 6.1 60E-1 4 7.241 E-1 1 7.373E-1 1 1.030E-1 4-1 .OOOE+00 0.000E+00 0.000E+00 Ba-140 GONADS 8.410E-15 5.451E-12 9.607E-11 1.910E-16-1.OOOE+004.300E-10 9.960E-10 BREAST 9.640E-1 5 5.280E-1 2 9.305E-11 11.850E-1 6-1 .OOOE+00 2.870E-1 0 1.590E-1 0 LUNGS 8.270E-1 5 4.852E-1 2 8.550E-1 1 1.700E-1 6-1 .000E+00 1.660E-09 6,630E-1 1 RED MARR 7.930E-15 4.880E-12 8.601E-11 1.710E-16-1.000E+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-1 55.1 09E-1 29.003E-11 11.790E-1 6-1 .OOOE+00 2.560E-1 05.250E-1 1 REMAINDER 7.890E-1 5 4,766E-1 2 8.399E-1 11.670E-1 6-1 .000E+00 1.41 OE-09 7.370E-09 EFFECTIVE 8.580E-1 5 5.1 37E-1 2 9.053E-1 11.800E-1 6-1 .000E+00 1.01 OE-09 2.560E-09 SKIN(FGR) 2.520E-1 4 5.565E-1 1 9.808E-1 0 1.950E-1 5-1 .000E+00 0.OOOE+00 0.000E+00 La-140 GONADS 1.1 40E-1 3 6.027E-1 1 4.425E-1 0 2.240E-1 5-1 .000E+00 4.540E-1 0 1.340E-09 BREAST 1.290E-1 3 5.758E-1 1 4.228E-1 0 2.1 40E-1 5-1 .OOOE+00 1.450E-1 0 1.800E-1 0 LUNGS 1.150E-1 3 5.596E-1 1 4.109E-1 0 2.080E-1 5-1.OOOE+00 4.210OE-09 4.01 OE-1 1 RED MARR 1.1 40E-1 3 5.731 E-1 1 4.208E-1 0 2.130E-1 5-1.OOOE+00 2.140E-1 0 2.810OE-1 0 BONE SUR 1.690E-13 7.776E-1 1 5.709E-10 2.890E-15-1.OOOE+00 1.410E-10 9.770E-1 1 THYROID 1.180E-1 3 5.462E-1 1 4.01 OE-1 0 2.030E-1 5-1 .000E+00 6,870E-1 1 6.400E-1 2 REMAINDER 1.11OE-13 5.569E-11 4.089E-10 2.070E-15-1.000E+00 2.120E-09 6.260E-09 EFFECTIVE 1.170E-13 5.812E-1 14.267E-10 2.160E-15-1 .OOOE+00 1.310E-09 2.280E-09 SKIN(FGR) 1.660E-1 3 2.21 7E-1 0 1.628E-09 8.240E-1 5-1 .OOOE+00 0.OOOE+00 0.OOOE+00 La-i141 GONADS 2.330E-15 7,315E-13 9.675E-13 4.740E-17-1 .OOOE+00 1.O1OE-1 13.770E-12 BREAST 2.640E-1 5 7,007E-1 3 9.267E-1 3 4.540E-1 7-1 .000E+00 9.840E-1 2 7.070E-1 3 LUNGS 2.340E-15 6.713E-13 8.879E-13 4.350E-17-1,OOOE+00 6.460E-10 2.720E-13 RED MARR 2.31 GE-iS5 6.852E-1 3 9.063E-1 3 4.440E-1 7-1 .OOOE+00 2.930E-1 11.070E-1 2 BONE SUR 3.490E-15 9.923E-13 1.312E-12 6.430E-17-1.OOOE+00 1.200E-10 6.060E-13 THYROID 2.390E-1 56.590E-1 38.71 6E-1 34.270E-17-1 .OOOE+00 9.400E-1 25.290E-1 4 REMAINDER 2.260E-1 5 6.682E-1 3 8.838E-1 3 4.330E-1 7-1 .OOOE+00 2.280E-1 0 1.240E-09 EFFECTIVE 2.390E-1 5 7.007E-1 3 9.267E-1 3 4.540E-1 7-1 .OOOE+00 1.570E-1 0 3.740E-1 0 SKIN(FGR) 6.580E-14 1.667E-10 2.204E-10 1.080E-14-1.OOOE+00 0.OOOE+00 0.OOOE+00 La-142 GONADS 1.400E-1 3 1.978E-1 1 2.034E-1 1 2,540E-1 5-1 .OOOE+00 1.660E-1 1 6.990E-1 1 BREAST 1.570E-1 3 1.885E-1 1 1.938E-11I 2.420E-1 5-1.OOOE+00 1.130E-1 1 1.540E-1 1 LUNGS 1.420E-1 3 1.846E-1i1 1.898E-1 1 2.370E-1i5-1.OOOE+00 3.01 OE-1 0 8.400E-1 2 RED MARR 1.420E-1 3 1.900E-11I 1.954E-1 1 2.440E-1 5-1.OOOE+00 1.360E-1 1 1.930E-1 1 BONE SUR 1.950E-1 3 2.484E-1 1 2.554E-1 1 3.190E-1 5-1.OOOE+00 1.11 OE-i 1 7.400E-1 2

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Project.' Nine Mile Point Nuclear Station Unit: -1 Disposition; QJA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21 C096 0 Ref.

THYROID 1.450E-1 3 1.768E-1l1 1.818E-1 1 2.270E-1 5-1.OOOE+00 8.740E-1 2 1.160E-1 2 REMAINDER 1.380E-1 3 1.853E-1 1 1.906E-1 1 2.380E-15-1.OOOE+00 8.070E-1 1 5.200E-1 0 EFFECTIVE 1.440E-1 3 1.916E-1 1 1.970E-1 1 2.460E-15-1 .OOOE+00 6.840E-1 1 1.790E-1 0 SKIN(FGR) 2.160E-13 9.11 1E-1 1 9.368E-11 11.170E-14-1 .OOOE+00 0.000E+00 0.000E+00 Ce-141 GONADS 3.380E-1 5 2.213E-1 2 4.332E-1 1 7.710OE-1 7-1 .OOOE+00 5.540E-1 11.080E-1 0 BREAST 3.930E-1 5 2.170E-1 2 4.247E-1 1 7.560E-1 7-1 .OOOE+00 4.460E-1 11.11 iCE-i 1 LUNGS 3.170E-1 5 1.951 E-1 2 3.820E-1 1 6.800E-1 7-1.CCCE+OC 1.670E-C8 1.43CE-1 2 RED MARR 2.830E-1 5 1.86CE- 12 3.641 E-1 1 6.480E- 17-1.CCCE+CC 8.960E-1 1 3.390E-1 1 BONE SUR 9.41CE-15 5.166E-121l0llE-iC 1.800E-16-1.CCCE+CO 2.54CE-1C 2.300E-11 THYROID 3.350E-15 2.003E-12 3.922E-11 6.980E-17-1.CCCE+CC 2.55CE-11 1.800E-13 REMAINDER 2.980E-1 51 .894E-1 23.708E-1 16.600E-1 7-1 .C0CE+C 1.260E-09 2.500E-09 EFFECTIVE 3.43CE-1 52.11 8E-1 24.1 46E-1 17.380E-1 7-1 .CCOE+CC 2.420E-09 7.830E-1 C SKIN(FGR) 1.020E-14 3.788E-1 2 7.41 6E-1 1 1.320E-1 6-1 .COOE+00 C.CCCE+00 C.COCE+OC Ce-i 43 GONADS 1.280E-1 4 7.900E-1 2 4.958E-1 1 2.980E-1 6-1.COOE+CC 7.530E-1 1 2.120E-1 0 BREAST 1.470E-14 7.688E-1 2 4.825E-1 1 2.900E-1 6-1 .CCCE+00 1.660E-1 1 2.320E-1 1 LUNGS 1.230E-14 6.893E-1 2 4.325E-1 1 2.600E-1 6-1,.OCOE+00 3.880E-09 3.820E-1 2 RED MARR 1.170E-1 4 6.787E-1 2 4.259E-1 1 2.560E-1 6-1 .COCE+00 2.960E-1 1 5.070E-1 1 BONE SUR 2.520E-14 1.323E-11 8.302E-11 4.99CE-16-1.OOOE+00 1.640E-11 1.610E-11 THYROID 1.280E-14 7.21 1E-1 2 4.525E-1 1 2.720E-16-1 .OOCE+CC 6.230E-12 4.350E-13 REMAINDER 1.1 70E-1 4 6.734E- 2 4.226E-i 1 2.54CE-i 6-i .CCE+CC 1.420E-09 3.890E-09 EFFECTIVE 1.290E-14 7.396E-1 2 4.642E-1 1 2.79CE-i 6-i .CCCE+CC 9.160E-10C 1.230E-C9 SKIN(FGR) 3.960E-1 4 1.058E-10C 6.638E-10C 3.990E-1 5-i .CCE+CC C.CCCE+CC C.CCCE+CC Ce-144 GONADS 2.725E-15 6.328E-13 1.319E-1i1 6.088E-17-1.CCCE+00 2.390E-10 6.987E-i11 BREAST 3.1 29E-15S 6.274E-1331.307E-1 1 5.922E-i 7-i .CCE+CC 3.480E-10C 1.223E-1 1 LUNGS 2.639E-15 5.228E-13 1.089E-1i1 5.362E-17-i.CCCE+00 7.911E-07 6.551E-12 RED MARR 2.5C7E-1 54.755E- 3 9.907E- 2 5.247E-i 7-1 .CCCE+CC 2.880E-09 8.923E-i11 BONE SUR 5.441 E-i5 1.646E-12 3.429E-i111.127E-16-i .CCCE+CC 4.720E-09 1.280E-iC THYROID 2.753E-1 5 5.529E-1 3 1.1 52E-1 1 5.41 8E-1 7-1 .CCCE+CC 2.920E-1 C5.1 54E-1 2 REMAINDER 2.534E-1 5 5.086E-1 3 1.06CE-1 1 5.283E-1 7-1 .CCCE+CC 1.910CE-08 1.890E-08 EFFECTIVE 2.773E-1 5 5.909E-1 3 1.231 E-1 1 5.766E-1 7-1.COCE+CC 1.01 OE-07 5.711 E-09 SKIN(FGR) 8.574E-14 7.648E-1 3 1.594E-1 1 1.25CE-14-1.COOE+CC C.CCCE+CC C.CCCE+CC Pr-I 43 GONADS 2.1 3CE-1 72.264E-1 44.C32E-1 37.93CE-1 9-1 .CCCE+CC 4.37CE-1 88.990E-1 6 BREAST 2.550E-17 2.330E-1 4 4.149E-1 3 8.1 6CE-1 9-1 .CCCE+CC 2.220E-1 8 1.090E-1 8 LUNGS 1.860E-17 1.642E-14 2.923E-13 5.750E-19-1.CCCE+00 1.330E-08 1.910E-19 RED MARR 1.620E-1 7 1.493E-14 2.659E-1 3 5.230E-1 9-1 .OOCE+0O 1.480E-1 11.030E-1 2 BONE SUR 5.930E-17 5.454E-14 9.711E-13 1.910E-18-1.OOCE+CC 1.490E-11 1.030E-12 THYROID 2.050E-1 7 1.802E-1 43.208E-1 36.31 CE-i 9-1 .COOE+0 1.680E-1 82.660E-20 REMAINDER 1.760E-1 7 1.642E-1 42.923E-1 35.75CE-1 9-1 .CO0E+C 1.970E-09 4.220E-C9 EFFECTIVE 2.100CE-1 7 2.002E-1 4 3.564E-1337.01 CE-i 9-1 .CCCE+CC 2.1 90E-09 1.270E-09 SKIN(FGR) 1.760E- 4 5.711 E-11 11.01 7E-09 2.CCCE-1 5-1 .CCCE+CC C.CCCE+CC C.CCCE+C Nd-147 GONADS 6.130E-15 4.218E-12 7.235E-1i 1.480E-16-1.CCCE+CC 8.4iCE-11 1.790E-10 BREAST 7.1 2CE-i 54.1 32E-1 27.C88E-11ii.450E-1 6-1 .CCCE+CC 3.45CE-11 11.870E-1 1 LUNGS 5.820E-1 53.648E- 2 6.257E-11 11.28CE-1 6-1 .COCE+C 1.060E-C8 2.44CE-1 2

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Project. Nine Mile Point Nuclear Station Unit: -1 Disposition: t3A Originator/Date Reviewer/Date No.

-Calculation Revision J.Metcalf 12112106 Appendix E H21C0096 0 RED MARR 5.400E-15 3.505E-12 6.013E-11 1.230E-16-1.000E+00 9.190E-11 5.050E-11 BONE SUR 1.320E-14 8.265E-1 21.41 8E-1 02.900E-1 6-1 .000E+00 3.260E-1 02.220E-1 1 THYROID 6.120E-15 3.876E-12 6.648E-11 1.360E-16-1.000E+00 1.820E-11 2.640E-13 REMAINDER 5.530E-1 5 3.562E-1 2 6.111 E-1 11.250E-1 6-1 .000E+00 1.760E-09 3.760E-09 EFFECTIVE 6.190E-1 5 3,961 E-1 2 6.795E-11I 1.390E-1 6-1.000E+0O 1.850E-09 1.180E-09 SKIN(FGR) 1.950E-14 3.135E-1 1 5.377E-10 1.100E-1 5-1 .000E+00 0.000E+00 O.OOOE+00 Np-239 GONADS 7.530E-15 4.691 E-1 24.380E-11 11.710E-16-1 .000E+00 7.450E-1 1 1.620E-10 BREAST 8.730E-1 5 4.636E-1 2 4.329E-1 1 1.690E-1 6-1 .000E+00 1.630E-1 1 1.720E-1 1 LUNGS 7.180E-15 4.1 15E-12 3.842E-11 11.500E-16-1.OOOE+O002.360E-09 2.400E-12 RED MARR 6.500E-1 5 4.005E-1 2 3.740E-1 1 1.460E-1 6-1 .OOOE+00 2.080E-1 0 4.660E-1 1 BONE SUR 2.000E-14 1.001 E-1 1 9.349E-1 1 3.650E-1 6-1 .000E+00 2.030E-09 3.590E-1 1 THYROID 7.520E-15 4.197E-12 3.919E-11 1.530E-16-1.OOOE+0O 7.620E-12 2.070E-13 REMAINDER 6.760E-1 54.005E-1 23.740E-11 11.460E-1 6-1 .OOOE+00 9.590E-1 02.770E-09 EFFECTIVE 7.690E-15 4.471 E-12 4.175E-1 1 1.630E-16-1.OOOE+00 6.780E-10 8.820E-10 SKIN(FGR) 1.600E-1 47.21 5E-1 26.737E-1 1 2.630E-1 6-1 .000E+00 0.000E+00 0.OOOE+0O Pu-238 GONADS 6.560E-18 4.291E-14 9.O11E-13 1.490E-18-1.000E+00 1.040E-05 2.330E-09 BREAST 1.270E-17 5.558E-14 1.167E-12 1.930E-18-1.OOOE+00 4.400E-1 1.800E-13 LUNGS 1.060E-1 82.267E-1 54.759E-1 47.870E-20-1 .OOOE+00 3.200E-04 8.640E-1 4 RED MARR 1.680E-1865.587E-1 51.1 73E-1 31 .940E-1 9-1 .OOOE+00 5.800E-05 1.270E-08 BONE SUR 9.300E-18 3.514E-14 7.378E-13 1.220E-18-1.000E+00 7.250E-04 1.580E-07 THYROID 4.01 OE-1 89.792E-1 52.056E-1 33.400E-1 9-1 .000E+00 3.860E-1 07.990E-1 4 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-1 8 2.41 3E-1 4 5.068E-1 3 8.380E-1 9-1 .OOOE+00 7.790E-05 1.340E-08 SKIN(FGR) 4.090E-1 7 2.776E-1 3 5.830E-1 2 9.640E-1 8-1 .OOOE+00 0.OOOE+00 0.000E+00 Pu-239 GONADS 4.840E-1 8 1.768E-1 4 3.71 3E-1 3 6.1 40E-1 9-1 .OOOE+00 1.200E-05 2,640E-09 BREAST 7.550E-18 2.238E-14 4.699E-13 7.770E-19-1.000E+00 3.990E-10 1.210E-13 LUNGS 2.650E-1 8 2.267E-1 5 4.760E-14 7.870E-20-1 .OOOE+00 3.230E-04 7.890E-1 4 RED MARR 2.670E-18 3.456E-15 7.258E-14 1.200E-19-1.000E+00 6.570E-05 1.410E-08 BONE SUR 9.470E-18 1.673E-14 3.514E-13 5.810E-19-1.OOOE+00 8.210E-04 1.760E-07 THYROID 3.880E-18 5.126E-15 1.077E-13 1.780E-19-1.OOOE+00 3.750E-10 7.500E-14 REMAINDER 2.860E-1 8 4.838E-1 5 1.01 6E-1331.680E-1 9-1 .OOOE+00 3.020E-05 2.1 20E-08 EFFECTIVE 4.240E-1 8 1.057E-1 4 2.220E-1 3 3.670E-1 9-1 .OOOE+00 8.330E-05 1.400E-08 SKIN(FGR) 1.860E-17 1.057E-1 3 2.220E-1 2 3.670E-1 8-1 .000E+00 0.000E+00 0.000E+00 Pu-240 GONADS 6.360E-1 8 4.118E-1 4 8.649E-1 3 1.430E-1 8-1.000E+00 1.200E-05 2.640E-09 BREAST 1.230E-1 7 5.328E-1 4 1.1 19E-1221.850E- 18-1 .OOOE+00 4.330E-1 0 1.730E-1 3 LUNGS 1.090E-1 8 2.249E-1 5 4.723E-1 4 7.81 OE-20-1 .OOOE+00 3.230E-04 8.220E-1 4 RED MARR 1.650E-18 5.386E-15 1.131E-13 1.870E-19-1.OOOE+00 6.570E-05 1.410E-08 BONE SUR 9.260E-1 83.398E-1 47.1 37E-1 31.1 80E-1 8-1 .OOOE+00 8.21 OE-04 1.760E-07 THYROID 3.920E-18 9.446E-15 1.984E-13 3.280E-19-1.OOOE+00 3.760E-10 7.510E-14 REMAINDER 1.960E-1 8 8.870E-1 5 1.863E-1 3 3.080E-1 9-1 .OOOE+00 3.020E-05 2.1 30E-08 EFFECTIVE 4.750E-1 8 2.31 3E-1 4 4.857E-1 3 8.030E-1 9-1 .OOOE+00 8.330E-05 1.400E-08 SKIN(FGR) 3.920E-1 7 2.644E-1 3 5.552E-1 2 9.1 80E-1 8-1 .000E+00 0.OOOE+00 O.OOOE+00 Pu-241 GONADS 7.1 90E-20 6.653E-1 7 1.396E-1 5 2.31 OE-21 -1.OOOE+00 2.760E-07 5.660E-1 1

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EOriginator/Date Project: Nine Mile Point Nuclear Station J.Metcalf 12/12/06 Rdviewer/Date Appendix E Unit: -1

-FCalculation No.

H21 C096 Disposition- PJIA Revision 0

BREAST 8.670E-20 7.229E-1 7 1.517E-1 5 2.510OE-21 -1.000E+00 2.140E-11I 2.790E-1 5 LUNGS 6.480E-20 4.090E-1 7 8.584E-1 6 1.420E-21 -1.000E+00 3.1 8011-06 4.480E-1 5 RED MARR 5.630E-20 4.003E-1 7 8403E-1 61 .390E-21 -1.000E+00 1.430E-06 2.780E-1 0 BONE SUR 2.190E-19 1.385E-16 2.908E-154.810E-21-1.000E+0O 1.780E-05 3.480E-09 THYROID 6.980E-20 4.522E-17 9.491E-16 1.570E-21-1.000E+00 9.150E-12 1.010E-15 REMAINDER 6.090E-20 4.291 E-1 7 9.007E-1 6 1.490E-21 -1.000E+00 6.020E-07 1.850E-1 0 EFFECTIVE 7.250E-20 5.558E-1 7 1.1 67E-1 5 1.930E-21 -1.000E+00 1.340E-06 2.070E-1 0 SKIN(FGR) 1.1 70E-1 92.033E-1 64.268E-1 57.060E-21 -1.000E+00 0.000E+00 0.000E+00 Am-241 GONADS 8,580E-1 69.360E-1 31 .966E-1 13.250E-1 7-1 .000E+00 3.250E-05 2.700E-07 BREAST 1.070E-1 51.01 4E-1 22.1 29E-1 1 3520E-1 7-1 .000E+00 2.670E-09 2.620E-1 1 LUNGS 6.740E-1 65.789E-1 31.21 SE-i112.01 0E-1 7-1 .000E+00 1.840E-05 3.360E-1 1 RED MARR 5.210E-164.838E-13 1.016E-11 1.680E-17-1.000E+00 1.740E-04 1.450E-06 BONE SUR 2.870E-1 52.678E-1 25.625E-1 19.300E-1 7-1 .000E+00 2.1 70E-03 1.81 OE-05 THYROID 7.830E-1 6 6.365E-1 3 1.337E-1 1 2.21 OE-1 7-1 .OOOE+00 1.600E-09 1.320E-1 1 REMAINDER 6.340E-1 6 5.933E-1 3 1.246E-1 1 2.060E-1 7-1 .000E+00 7.820E-05 6.660E-07 EFFECTIVE 8.180E- 16 7.920E- 13 1.663E-1 1 2.750E-1 7-1.000E+00 1.200E-04 9.840E-07 SKIN(FGR) 1.280E-1 5 2.396E-1 2 5.032E-1 1 8.320E-1 7-1 .000E+00 0.000E+00 0.OOOE+00 Cm-242 GONADS 7.830E-1 8 4.893E-1 4 1.01 3E-1 2 1.700E-1 8-1 .000E+00 5.700E-07 5.200E-09 BREAST 1.480E-17 6.159E-14 1.275E-12 2.140E-18-1.OOOE+00 9.440E-10 8.950E-12 LUNGS 1.1 30E-1 8 3.022E-1 5 6.257E-14 1.050E-1 9-1 .000E+00 1.550E-05 8.840E-1 2 RED MARR 1.890E-18 6.562E-15 1.359E-13 2.280E-19-1.000E+00 3.900E-06 3.570E-08 BONE SUR 1.060E-1 74.231 E-1 48.759E-1 31 .470E-1 8-1 .OOOE+00 4.870E-05 4.460E-07 THYROID 4.910E-18 1.261E-14 2.610E-13 4.380E-19-1.OOOE+00 9.410E-10 8.820E-12 REMAINDER 2.270E-1 8 1.079E-1 4 2.235E-1 3 3.750E-1 9-1 .OOOE+00 2.450E-06 4.020E-08 EFFECTIVE 5.690E-1 8 2.751 E-1 4 5.697E-1 3 9.560E-1 9-1 .OOOE+00 4.670E-06 3.1 00E-08 SKIN(FGR) 4.290E-1 7 2.700E-1 3 5.589E-1 2 9.380E-1 8-1 .OOOE+00 0.OOOE+00 0.OOOE+00 Cm-244

.GONADS 6.900E-1 8 4.522E-1 4 9.492E-1 3 1.570E-1 8-1 .OOOE+00 1.590E-05 1.330E-07 BREAST 1.330E-1 7 5.702E-1 4 1.197E-1 2 1.980E-1 8-1.000E+00 1.040E-09 8.820E-1 2 LUNGS 7.080E-1 9 2.592E-1 5 5.441 E-1 4 9.000E-20-1 .000E+00 1.930E-05 8.81 OE-1 2 RED MARR 1.460E-18 5.875E-15 1.233E-13 2.040E-19-1.OOOE+00 9.380E-05 7.820E-07 BONE SUR 8.820E-18 3.859E-14 8.1O1E-13 1.340E-18-1.OOOE+00 1.170E-03 9.770E-06 THYROID 4.1 90E-1 81. 146E-1 42.406E-1 33.980E-1 9-1 .000E+00 1.01 OE-09 8.440E-1 2 REMAINDER 1.810E-18 9.821E-15 2.062E-13 3.410E-19-1.OOOE+00 4.780E-05 4.150E-07 EFFECTIVE 4.91 0E-1 8 2.529E-1 4 5.308E-1 3 8.780E-1 9-1.000E+00 6.700E-05 5.450E-07 SKIN(FGR) 3.91 0E-1 72.506E-1 35.260E-1 28.700E-1 8-1 .OOOE+00 0.OOOE+00 0.OOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D38-(Next _D39 Project: Nine Mile Point Nuclear Station Unit: -1 Disposition- _!LA Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21 C096 0 Appendix D-3: Radtrad Output (.0O) file, NMPICRDA.oO (Excerpt)

Cumulative Dose Summary EA-B LPZ CR Time Thyroid TEDE Thyroid TEDE Thyroid TEDS (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0 .DOC0 0. OOOOE+00 0. OOOOE+O0 0.00005+00 0. 00005+00 0. CCOOE+0C 0. OOCOE+00 0.001 8. 4437E-07 1. 5197E-07 1. 7791E-08 3. 2020E-09 2 . 2162E-07 8 .5548E-C09 0.401 3 . 0014E-01 4.3980E-02 6 . 3241E-03 9. 2667E-04 6.2168E-01 2 .3252E-02 0 .701 7 .5271E-01 9 .7130E-02 1. 5860E-02 2. 0466E-03 1 . 5716E+00 5.7527E-02 1.001 1. 2863E+00 1. 5223E-01 2 . 7103E-02 3 .2075E-03 2 .6942E+00 9.7233E-02 1.230 1 . 7187E+00 1. 9357E-01 3. 6213E-02 4.0786E-03 3 .6046E+00 1. 2906E-01 1.630 2. 4932E+00 2 . 6314E-01 3 .1080CE-0l 2. 8743E-02 6. 3823E+00 2 .2507E-01 1.930 3. 0772E+00 3 . 1273E-01 5. 1782E-01 4 . 632 1E-02 8 .5989E+00 3. 0120E-01 2.230 3 . 6581E+00 3 . 6009E-01 7. 2376E-01 6. 3113E-02 1 . 0804E+01 3. 7649E-01 2.530 4.2337E+00 4 .0534E-01 9. 2783E-01 7. 9155E-02 1. 2989E+/-01 4 . 5070E-01 2.830 4 .8030E+00 4 .4861E-01 1.-1297E+00 9. 4494E-02 1 . 5151E+01 5. 23755-Cl 3 . 130 5. 3657E+00 4 . 9004E-01 1 . 3291E+00 1. 0918E-01 1. 7286E+01 5. 9562E-01 3 .430 5.-9215E+00 5. 2978E-01 1. 52625÷00 1.2327E-01 1 . 8929E+01 6. 5070E-Cl 3.730 6. 4704E+00 5 . 6794E-01 1. 7208E+00 1. 3680E-01 2.0085E+01 6 . 8 93 3 E-0 1 4.030 7 . 0126E+00 6 .0466E-0l 1 .913 OE÷C 0 1. 4982E-01' 2 . 122 8E+01 7. 2734E-0l 4.330 7 .5480E+00 6. 4003E-01 2 . 102 8E+00 1.623 6E-01 2 .2356E+01 7 . 6476E-01 4.630 8. 0769E+00 6.7416E-01 2 .2903E+00 1 .7446E-01 2 .3470E+01 8 . 0162E-Cl 4 .930 8. 5992E+00 7 .0713E-01 2. 4755E+00 1 . 8614E-01 2 .4571E+01 8 .3791E-01 5.230 9. 115 1E+00 7. 3902E-01 2.6584E+00 1. 9745E-01 2 .5658E+01 8. 7367E-01 5.530 9. 6247E+00 7 .6991E-01 2 . 6691E+00 1. 9810E-01 2 .673 2E+01 9 .0891E-01 5.830 1. 012 8E+01 7 .99855-Cl 2 .6797E+00 1. 9873E-01 2 .7793E+01 9. 4364E-01

6. 130 1. 0625E+01 8 .2891E-01 2.6902E+00 1. 9934E-01 2 .8840E+01 9 .7787E-01 6.430 1 . 1117E+01 8.5714E-01 2 .7005E+00 1 .9994E-01 2 . 9876E+01 1. 0116E+00 6.730 1. 1602E+01 8 .8459E-01 2.7108E+00 2 .0 05 2 E-0 1 3 .0898E+01 1.0449E+00

7. 030 1. 2081E+01 9 .1131lE-01 2 .7209E+00 2 . 0108E-01 3 . 1909E+01 1. 0777E+00 7.330 1. 2555E+01 9. 3733E-01 2 .7308E+00 2 . 0163E-01 3 .2907E+01 1 . 1101E+00 7.630 1. 3023E+01 9. 6269E-01 2 .7407E+00 2 . 02165-Cl 3 . 3893E+01 1. 142 1E÷O00 7.930 1 . 3486E+01 9. 8743E-01 2 .7504E+00 2 .0268E-01 3.4868E+01 1 . 173 65+/-O00 8.000 1 .3593E+01 9. 9311E-01 2 .7527E+00 2 .0280E-01 3 .5093E+01 1. 1809E+00 8.300 1. 3593E+01 9 .9311E-01 2 .7560E+00 2 .0304E-01 3 .5527E+01 1. 194 9E+00 8.600 1. 3593E+01 9 . 9311E-01 2 .7592E+00 2 . 0328E-01 3. 5851E+01 1.2053E+00 8 .900 1 .3593E+01 9. 9311E-01 2.7625SE+00 2 . 0351E-01 3. 6171E+01 1. 2156E+00 9.200 1. 3593E+01 9 .9311E-01 2 .7656E+00 2 .0373E-01 3. 6487E+01 1.2258E+00 9.500 1. 3593E+01 9. 9311E-01 2. 7688E+00 2 .0394E-Cl 3 . 6799E+01 1.2358E+00 9.800 1. 3593E+01 9. 9311E-01 2 .7719E+00 2 .0415E-01 3 .7108E+01 1.2457E+/-00

10. 100 1. 3593E+01 9. 9311E-01 2 .7749E+00 2 .0436E-01 3 . 7414E+01 1.2555E+00 10.400 1. 3593E+01 9. 9311E-01 2 .7780E+00 2 . 0456E-01 3.7715S+01 1.2652E+00

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: r-J Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 12/12/06 Appendix E H21 C096 0 ]

Ref.

24.000 1.3593E+01 9.9311E-01 2.8850E+00 2.1079E-01 4.8368E÷01 1.6037E+00 96.000 1.3593E+01 9.9311E-01 2.8850E+00 2.1079E-01 4.8548E+01 1.6094E+00 720.000 1.3593E+01 9.9311E-01 2.8850E+00 2.1079E-01 4.8S48E+O1 1.6094E÷00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.4 2.2553E-01 3.6849E+/-00 3.4186E-01

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Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: O/A, Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 12/13/06 Check of Appendix D H21CO96 0 Appendix E: Check Calculation Using the STARDOSE Computer Code for Case 2 This appendix presents check calculation results for the CRDA analysis using the Polestar STAIRDOSE computer code (Reference E-1) to check the RADTRAD results for CRDA 2. The Design Input Data and Assumptions are the same as those used in the main body of the calculation.

The AST application described below for the CRDA is consistent with Reference E-2.

STARDOSE Calculation The STARDOSE LIBFILE.TXT file is included as Attachment E-1.

The core inventories listed in Column 5 of the LJIBFIILEI1.TXT are from Reference E-3. The Dose Conversion Factors (Column 8 for whole body and Column 12 for CEDE) are the same as in the main body of the calculation. Decay constants (per second) come from Reference E-4.

Knowing that the damaged fuel rod fraction is 2.58%, that none of this fraction is assumed to melt, and that the peaking factor is 1.8, one can calculate the release fractions for the difference radionuclide groups.

For instance, the gap and fuel releases for the iodine group are respectively 10% and 50%. 10% of the iodine reaches the condenser and 10% of the iodine in the condenser remains airborne. Therefore, the release fractions for the iodine group are as follows:

From the core to the condenser:

(0.0258) x 1.8 x [(10% x 100%) + (50% x 0%)] x 10% = 4.644E-04 Fraction airbomne in the condenser available for release:

10% x 4.644E-04= 4.644E-05 The release fractions used in STARDOSE for Case 2 are shown in the table below:

Radionuclide Release Activity That Fraction of Total Available Group Fraction from Reaches the Condenser Release (with Gap to Coolant Condenser Activity peaking factor of Available for 1.8 and 850 pins Release to failed out of Environment 22,080)

Noble Gas 10% 100% 100% 4.644E-03 Iodine 10% 10% 10% 4.644E-05 Cs, Rb 12% 1% 1% 5.573E-07

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Project. Nine Mile Point Nuclear Station Unit: -1 Disposition- */A Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 12/1 3/06 Check of Appendix D H21 C096 0 Ref.

Conclusions The dose agreement for all cases is adequate. The STARDOSE run confirms the RADTRAD results for the CRDA, Case 2.

The following table compares TEDE values (in rem) calculated from RADTRAD versus STARDOSE.

Case 2 Case 2

________RADTRAD STARDOSE EA.B 0.37 0.34 LPZ 0.23 0.23 Control Room 1.72 1.66 Appendix References E-1. "STARDOSE Model Report", Polestar Applied Technology, Inc., PSATCI09.03, January 1997.

E-2. "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", US NRC Regulatory Guide 1.183, Revision 0, July 2000.

E-3. PSAT 4026CF.QA.03, "Design Data Base for Application of the Revised DBA Source Term to Nine Mile Point Unit I", Revision 0.

E-4 NTJREG/CR-5 106 (Manual for TACT5 - Version SAIC 9/23/87), File MLV{RJCRP.30.

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Oiiaor/Date Reviewer/Date Calculation No. Revision Hutla12/13/06 Check of Appendix D IH21CO96 10 Ref.

Attachment E-1: STARDOSE Library File for Case 2 (LIBFILEI .TXT) n-isotopes 76 njisotope..groups 11 KI-83m NGas NONE NONE 3.27E+031,05E-04 0 5.55E-06 0 0 0 Kr85m NGas NONE NONE 6.82E+034.30E-05 0 2.77E-02 0 0 0 Kr-85 NGas NONE NONE 3.93E+022,05E-09 0 4.40E-04 0 0 0 Kr87 NGas NONE NONE 1.30E+041.51 E-04 0 1.52E-01 0 0 0 Kr-88 NGas NONE NONE l.83E+046.78E-05 0 5.01 E-0l1 0 8.36E+01 0 Kr89 NGas NONE NONE 2.22E+043.63E-03 0 3.23E-01 0 0 0 Xel3lm NGas NONE NONE 3.04E+026.74E-07 0 1.44E-03 0 0 0 Xel33m NGas NONE NONE l.63E+033.67E-06 0 5.07E-03 0 0 0 Xe1 33 NGas 1133Part NONE 5.27E+041.53E-06 0 5.77E-03 0 0 0 Xel35m NGas NONE NONE l.09E+047.56E-04 0 7,55E-02 0 0 0 Xe135 NGas 1135Part NONE l.91E+042.12E-05 0 4.40E-02 0 0 0 Xe137 NGas NONE NONE 4.80E+042.96E-03 0 3.03E-02 0 0 0 Xe138 NGas NONE NONE 4.50E+046.80E-04 0 2.13E-01 0 0 0 1131 Org Org-i NONE NONE 2.71 E+049.98E-07 0 6.73E-02 0 3.29E+040 11 320rg Org-l NONE NONE 3.92E+048.37E-05 0 4.14E-01 0 3.81 E+020 11 330rg Org-i NONE NONE 5.51 E+04 9.26E-06 0 1.09E-01 0 5.85E+030 11 340rg Org-1 NONE NONE 6.03E-'042.20E-04 0 4.81 E-01 0 1.31 E+020 11 350rg Org-i NONE NONE 5.16E+042.91E-05 0 3.07E-01 0 1.23E+030 1131Elem ElmI Tel 31m NONE 2.71 E+049.98E-07 0 6.73E-02 0 3.29E+040 11l32Elem ElmI Tel 32 NONE 3.92E+048.37E-05 0 4.14E-01 0 3.81 E+02 0 11l33Elem ElmI NONE NONE 5.51 E+04 9.26E-06 0 1.09E-01 0 5.85E+030 11l34Elem ElmI NONE NONE 6.03E+042.20E-04 0 4.81 E-01 0 1.31 E+02 0 11l35Elem ElmI NONE NONE 5.16E+042.91E-05 0 3.07E-01 0 1.23E+030 1131lPart PrtI NONE NONE 2.71 E+049.98E-07 0 6.73E-02 0 3.29E+04 0 11l32Part PrtI NONE NONE 3.92E+048.37E-05 0 4.14E-01 0 3.81 E+020 11l33Part PrtI NONE Xe133 5.51 E+04 9.26E-06 0 1,09E-01 0 5.85E+030 11l34Part Prtl NONE NONE 6.03E+042.20E-04 0 4.81 E-01 0 1.31E+020 1135Part Pd_ I NONE Xe135 5.16E+042.91E-05 0 3.07E-01 0 1.23E+030 Rb86 CsGrp NONE NONE 7.29E+01 4,30E-07 0 1.78E-02 0 6.62E+030 Cs134 CsGrp NONE NONE 7.29E+031.07E-08 0 2.80E-01 0 4.63E+040 Cs136 CsGrp NONE NONE 2.28E+036.12E-07 0 3.92E-01 0 7.33E+030

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(Next -E5-Project: Nine Mile Point Nuclear Station Unit: 1 Disposition: m/A Originator/Date Reviewer/Date Calculation No. Revision Hutla1 2/13/06 Check of Appendix D H21 C096 0 Ref.

Cs1 37 CsGrp NONE 8a137m 4.35E+037.32E-10 0 1.01 E-01 0 0 0 3.19E+040 0 0 0 0 0 Sb127 TeGrp NONE Te127 3.01 E+032.08E-06 0 1.23E-01 0 0 0 6.03E+030 0 0 0 0 0 Sb129 TeGrp NONE Tel 29 8.91 E+034.46E-05 0 2.64E-01 0 0 0 6,44E+020 0 0 0 0 0 Tel 27m TeGrp NONE NONE 4.05E+027.36E-08 0 5,44E-04 0 0 0 2.15E+040 0 0 0 0 0 Te127 TeGrp Sb1 27 NONE 3.OOE+032.06E-05 0 8.95E-04 0 0 0 3.18E+020 0 0 0 0 0 Tel 29m TeGrp NONE NONE 1,30E+032.39E-07 0 1.23E-02 0 0 0 2.40E+040 0 0 0 0 0 Te129 TeGrp Sb129 NONE 8.76E+031.66E-04 0 1.02E-02 0 0 0 7.73E+01 0 0 0 0 0 0 Tel3lm TeGrp NONE 1131lElem 3.97E+03 6.42E-06 0 2.76E-01 0 0 0 6.50E+030 0 0 0 0 0 Tel132 TeGrp NONE 11 32E~em 3.85E+04 2.46E-06 0 3.81 E-02 0 0 0 9.44E+030 0 0 0 0 0 Bal37m BaGrp Cs1 37 NONE 4.12E+034.53E-03 0 1.07E-01 0 0 0 0.OOE+000 0 0 0 0 0 Ba139 BaGrp NONE NONE 4.89E+041.40E-04 0 8.03E-03 0 0 0 1.72E+020 0 0 0 0 0 Bal4O BaGrp NONE Lal4O 4.71 E+046.30E-07 0 3.17E-02 0 0 0 3.74E+030 0 0 0 0 0 Mo99 NMtis NONE Tc99m 5.13E+042.92E-06 0 2.69E-02 0 0 0 3.96E+030 0 0 0 0 0 Tc99m NMtls Mo99 NONE 4.49E+043.20E-05 0 2,18E-02 0 0 0 3.26E+01 0 0 0 0 0 0 Ru003 NMtls NONE NONE 4.29E+042.04E-07 0 8.33E-02 0 0 0 8.96E+030 0 0 0 0 0 R0lO5 NMtls NONE RhlO5 3.O1E+044.34E-05 0 1.41E-01 0 0 0 4.55E+020 0 0 0 0 0 RulO6 NMtls NONE NONE l.76E+042.18E-08 0 3.85E-02 0 0 0 4.77E+050 0 0 0 0 0 RhlO5 NMtls RulO5 NONE 2.84E+045.45E-06 0 1.38E-02 0 0 0 9.55E+020 0 0 0 0 0 Y90 LaGrp Sr9O NONE 3.24E+033.OlE-06 0 7.03E-04 0 0 0 8.44E+030 0 0 0 0 0 Y91 LaGrp Sr9l NONE 3,18E+041.37E-07 0 9.62E-04 0 0 0 4.88E+040 0 0 0 0 0 Y92 LaGrp Sr92 NONE 3.40E+045.44E-05 0 4.81 E-02 0 0 0 7.81E+020 0 0 0 0 0 Y93 LaGrp NONE NONE 3,96E+041.91 E-05 0 1.78E-02 0 0 0 2.15E+030 0 0 0 0 0 Zr95 LaGrp NONE Nb95 4.46E+041.25E-07 0 1.33E-01 0 0 0 2.36E+040 0 0 0 0 0 Zr97 LaGrp NONE NONE 4.51E+041.14E-05 0 1.64E-01 0 0 0 4.33E+030 0 0 0 0 0 Nb95 LaGrp Zr95 NONE 4.48E+042.28E-07 0 1.38E-01 0 0 0 5.81E+030 0 0 0 0 0 Lal4O LaGrp Bal4O NONE 5.12E+044.78E-06 0 4.33E-01 0 0 0 4.85E+030 0 0 0 0 0 Lal4l LaGrp NONE Cel4l 4.45E+044.90E-05 0 8.84E-03 0 0 0 5.81E+020 0 0 0 0 0 La142 LaGrp NONE NONE 4.29E+041.25E-04 0 5.33E-01 0 0 0 2,53E+020 0 0 0 0 0 Pr143 LaGrp Ce143 NONE 3.97E+045.92E-07 0 7.77E-05 0 0 0 8.10E+030 0 0 0 0 0 Nd147 LaGrp NONE NONE 1.80E+047.31E-07 0 2.29E-02 0 0 0 6.85E+030 0 0 0 0 0 Am24l LaGrp NONE NONE 7.48E+005.08E-11 0 3.03E-03 0 0 0 4.44E+080 0 0 0 0 0 Cm242 LaGrp NONE NONE 1.85E+034,93E-08 0 2.11 E-05 0 0 0 1.73E+070 0 0 0 0 0 0m244 LaGrp NONE NONE 1.23E+021.21E-09 0 1.82E-05 0 0 0 2.48E+080 0 0 0 0 0 0e141 CeGrp Lal4l NONE 4.47E+042,47E-07 0 1.27E-02 0 0 0 8.95E+030 0 0 0 0 0

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page __E5___

(Next -E6-Project:' Nine Mile Point Nuclear Station Unit Disposition: m/A

[Originator/Date Reviewer/Date FCalculation No. Revision Hutla12/13/06 Check of Appendix D H21 C096 0 Ref.

0e143 CeGrp NONE Pr-143 4.11 E+04 5.83E-06 0 4.77E-02 0 0 0 3.39E+030 0 0 0 0 0 Ce144 CeGrp NONE NONE 3.70E+042.82E-08 0 1.03E-02 0 0 0 3.74E+050 0 0 0 0 0 Np239 CeGrp NONE NONE 5.78E+053.41E-06 0 2.85E-02 0 0 0 2.51 E+030 0 0 0 0 0 Pu238 CeGrp NONE NONE 1.45E+022.50E-10 0 1.81 E-05 0 0 0 2.88E+080 0 0 0 0 0 Pu239 CeGrp NONE NONE 1.34E+01 9.13E-1 3 0 1.57E-05 0 0 0 3.08E+080 0 0 0 0 0 Pu240 CeGrp NONE NONE 1.89E+01 3.36E-12 0 1.76E-05 0 0 0 3.08E+080 0 0 0 0 0 Pu241 CeGrp NONE NONE 5.49E+031.53E-09 0 2.68E-07 0 0 0 4.96E+060 0 0 0 0 0 Sr89 SrGrp NONE NONE 2.45E+041.59E-07 0 2.86E-04 0 0 0 6.51 E+03 0 0 .0 0 0 0 Sr9O SrGrp NONE Y90 3.14E+037.54E-10 0 2.79E-05 0 0 0 2.39E+050 0 0 0 0 0 Sr9l SrGrp NONE Y91 3.1OE+042.03E-05 0 1.82E-01 0 0 0 9.32E+030 0 0 0 0 0 Sr92 SrGrp NONE Y92 3.38E+047.1OE-05 0 2.51E-01 0 0 0 6.29E+020 0 0 0 0 0

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -E6-(Next __E7-Project.' Nine Mile Point Nuclear Station Unit: __I Disposition:- _IA Oiginator/Date Reviewer/Date Calculation No. Revision Check of Appendix D H21C096

[H. Pustulka 12/13/06 0

Attachment E-2: STARDOSE Main Input File for Case 2 edit time 00.001 0.5 1 1.23 1.5 23.23 481224 36 end-edit-time participating-isotopes Kr83m Kr85mn Kr85 Kr87 Kr88 Kr89 Xe13lm Xel33mn Xe133 Xe135mn Xe135 Xe137 Xe138 1131lOrg 1131lElemn 1131Part 11 320rg 11l32Elemn 1132Part 11 330rg ll33Elem 11l33Part ll34Org ll34Elemn 1134Part 11350rg 1135Elem 11l35Part Rb86 Cs134 Cs136 Cs137 Sb127 Sb129 Tel27m Te127 Tel29m Te129 Tel3lm Te132 8a137mn Ba139 Bal4O Mo99 Tc99mn RulO3 RulOS RulO6 RhlO5 Y90 Y91 Y92 Y93 Zr95 Zr97 Nb95 Lal4O LalW La142 Pr143 Nd147 Am241 Cm242 Cm244 cel41 0e143 ce144 Np239 Pu238 Pu239 Pu240 Pu241 Sr89 Sr9O Sr9l Sr92 end-participating-isotopes core thermal-power 3397 elemental-iodine -frac 0.97 organic-iodine -frac 0.03 particulate-iodine-frac 0.0 release-frac to_-control-volume SOURCE Time NGas I-Grp CsGrp TeGrp BaGrp NIVtls CeGrp LaGrp SrGrp 0.001 2.58 2.58 3.10 0 0 0 0 0 0 720 0 0 0 0 0 0 0 0 0 end to control volume end release-frac end--core control volume obj-type OBJCv name SOURCE air-volume 1.47e7 water volume 0 surface-area 0 has recirc filter false end-control-volume control-volume

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -E7_

(Next __E8-Project: Nine Mile Point Nuclear Station Unit: -1 Disposition:, ii/A Originator/Date Reviewer/Date Calculation No. FRevision H.Pustulka 12/13/06 Check of Appendix D H21 C096 0

lRe. II obj-type OBJCV name CONDENSER air volume 50000 water volume 0 surface-area 0 has recirc filter false end-control-volume control volume obj-type OBJ_-CR name ControlRoom air volume 135000 water volume 0 surface-area 0 has -recirc -filter false breathing-rate Time (hr) Value (cms) 720 0.00035 end-breathing-rate occupancy-factor Time (hr) Value (frac) 24

96. 0.6 720 0.4 end-occupancy-factor end-control-volume junction junction-type AIRJUNCTION downstream location AIRSPACE upstream CORE downstream SOURCE has filter false flow rate Time (hr) Value (cfm) 7201 end flow rate end-junction junction junction-type AIRJUNCTION down stream-locatio n AIRSPACE upstream SOURCE downstream CONDENSER has filter true flow rate

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -E8-(Next __E9-Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: 01/A Originator/Date Reviewer/Date Calculation No. Revision H. Pustulka 12/13/06 Check of Appendix D H21C096 Ref.

Time (hr) Value (cfm) 24 6860 720 0 end-flow-rate filter -efficiency Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0.9 0.9 0.9 0.99 0.99 end -filter -efficiency firac-4 daughter -resusp Time NobleGas Elem Iodine Org Iodine Partlodine Solubles Insolubles 720 1 1 0 0 0 0 end-frac_4_daughterjresusp end-junction junction junction-type AIRJUNCTION downstream-location AIRSPACE upstream CONDENSER downstream environment has-filter true flow-rate Time (hr) Value (cfim) 24 2000 720 0 end-flow-rate filter-efficiency Time NobleGas FElemlodine Orglodine Partlodine Solubles Insolubles 720 0 0.9 10.9 0.9 0.99 0.99 end-filter-efficiency frac-4daughterjresusp Time NobleGas FElem Iodine Orglodine Partlodine Solubles Insolubles 720 1 1 0 0 0 0 end-frac_4_daughter resusp X -over-Q..4_site~boundary Time (hr) Value (slm*3) 1.23 0.0 3.23 5.98e-5 720 0,0 endX-overQ_4_site-boundary X-over_-Q_4_Iow-population -zone Time (hr) Value (slm*3) 1.23 1,26e-6 5.23 2.12e-5

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -E9-(Next __El____

Project:- Nine Mile Point Nuclear Station Unit: __I Disposition: .PŽLA Reviewer/Date Calculation No. Revso Originator/Date H. Pustulka 12/13/06 Check of Appendix D H21CO96 8 1.26e-6 24 8.40e-7 96 3.45e-7 720 1.1 le-7 end_-X -over_-Q-4jow-population-zone X-over_0_4_-ctrl -room Time (hr) Value (s/m*3) 1.23 1.26e-4 3.23 2.27e-4 8 1.26E-4 24 4.30E-5 96 3.58E-5 720 2.59E-5 endX overQ_4_ctrl room end..Junction junction junction-type AIRJUNCTION down stream-location AIRSPACE upstream environment downstream ControlRoom has filter true flow rate Time (hr) Value (cfm) 720 1e6 end flow rate filter....efficiency Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0 0 0 0 0 end -filter-efficiency frac-4 daughter -resusp Time NobleGas Elemlodine Orglodine Pa~rtlodine Solubles Insolubles 720 1 1 0 0 0 0 end -frac_-4_-daughterjresusp end-junction junction junction-type AIRJUNCTION downstream location AIRSPACE upstream Control_-Room downstream environment has-filter false flow rate Time (hr) Value (cfm) 720 1e6 end flow rate X-over_0_4_ctrl-room

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -E10-(NextEliI)j Project:- Nine Mile Point Nuclear Station Unit: 1 Disposition: JŽh/LA Calculation No. Revision Friginator/Date H.Pustulka 12/13/06 Reviewer/Date Check of Appendix D H21C096 Ref.

Time (hr) Value (slm*3) 720 0 end_-X -overQ_4_ctrl-room X-over_-Q_-4_-site -boundary Time (hr) Value (slm*3) 720 0 end_-X -over_-Q_-4_-site -boundary X-overQ_4_low-population -zone Time (hr) Value (s/m*3) 720 0 end_-X -overQA Jlow-population-zone end-junction environment breathing-ratesb Time (hr) Value (cms) 8 0.00035 720 0.0 end -breathing-ratesb breath ing-ratejlpz Time (hr) Value (cms) 8 0.00035 24 0.00018 720 0.00023 end -breathing-rate-Ipz end-environment

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -El 1-(Next: Attachment 1)

Project: Nine Mile Point Nuclear Station Unit: -1 Disposition: wýJA Originator/Date Reiwer/Date - C No.

-alculation Revision H.Pustulka 12/13/06 Chck of Appendix D H21CO96 0 Attachment E-3: STARDOSE Results for Case 2(Excerpts) edit time 2.000000 CONDENSER air -space Kr83m 1. .49E+02 Kr85m 4 . 85E+02 Kr 85 3 .81E+01 Kr 87 4 . 25E+02 Kr88 1. 09E+03 edit time 36.000000 Control-Room thyroid wbody skin CEDE Total dose: 0 .OOE+000 7.96E-002 0 .OOE+000 1. 58E+000 Noble gas 0. OOE+000 7 .57E-002 0.005+000 6.525-002 Org iodine 0 .OOE+000 1. 16E-004 0. OOE+000 4 .51E-002 Elem iodine 0 . 00+000 3.76E-003 0 .OOE+000 1. 46E+000 Part iodine 0. OOE+000 0. 005+000 0. OOE+000 0 .OOE+000 Cesium 0.005+000 6. 86E-006 0. 005+/-000 7. 63E-003 Tellurium 0. 005+000 0 .OOE+000 0. 005+/-000 0. 005÷000 Barium 0. 005+000 9. SOE-007 0. OOE+000 0. OOE+000 Noble metal 0. OOE+000 0. OOE+000 0. OOE+/-000 0. 005+000 Lanthani des 0 .OOE+000 0. 005+000 0. 005+000 0. 005+000 Cerium 0. 00E+000 0 .OOE+000 0. 005+000 0 . OOE+000 Strontinum 0. 005+000 0. 005+000 0. 005+000 0. OOE+000 environment thyroid wbody skin CEDE EAB dose: 0. 005+000 2. 09E-001 0. OOE+000 I. 29E-001 LPZ dose: 0 .OOE+000 1. 26E-001 0.OOE+000 9. 56E-002 STAP.DOSE 1.01 (c) 1996-2002 Polestar Applied Technology, Inc.

Fri Nov 10 17:35:41 2006 Total elapsed hours: 0, mins: 0, secS: 3

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9 ?-1 C-094, -(P0 %/I)

AtTAC EtII:7 ~D~GNRIWi ON- EPR1 Document being design-verified: Lii DCP IXJCalc Lii Spec E3 NER El DBD L3 Other Doc#, Rev and

Title:

-H21C096, Revision 0: U1 CRDA, AST Methodology Extent of Design Verification (Briefly describe):

This calculation was design verified by 1)validating all input with respect to the input database (with the exception of the Dose Conversion Factors which were validated utilizing the FGR 11 and 12 parent documents), making sure that the appropriate input values were used; 2) assuring that all assumptions are conservative and conform to the Reg Guide 1.183 AST requirements; 3)validating the calculation methodology and calculation tools (i.e. spreadsheet) as being acceptable for the task; and 4) validating final results to make sure that they are as expected.

Method of Design Verification:

MR Design Review Lii Qualification Testing LII Alternate Calculations Lii Applicability of Proven Design Results of Design Verification:

ElI Fully acceptable with no issues identified LII Fully acceptable based on the following issues identified and resolved:

All input were appropriate and all assumptions valid (no further validation of assumptions are required). The calculation methodologies were appropriate for the task. All calculated values conform to as expected results.

The calculation made several assumptions which simplified the analysis. and also added significant conservatism. Among these conservatisms is the control room being essentially open to the environment, so that no Habitability Zone protections were taken into account (such as filtration, delayed inflow, etc.). Minor issues were commented upon and corrected prior to final draft of the calculation. The decay energy distribution found inApp.C did not match the reference C-i values as the ref.values had one less significant figure. However, this roundoff error does not affect the results, and therefore is acceptable. Also, the iron gamma attenuation values found inApp.C were based on a graph from ref. C-2. The values taken from the graph were examined and deemed to be close to what this reviewer independently obtained. As a secondary check of the attenuation values, this reviewer determined the energy dependent attenuation for iron utilizing reference material for the QAD-P5Z computer program. These values, using a Berger Buildup factor methodology, were within 10% of those presented inApp.C. Since the application of the App.C results do not require extreme accuracy, it is deemed that the attenuation factors used inApp.C are acceptable.

J Continuation Page Follows Discipline Involvement and Approvals:

Lead Design M.Berg C12/13/06 Verifier: C Name Signature Date Discipline Design Verifiers, if required:

N/A__ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _

Discinline Name Sianature Date

1/k The following questions are required to be addressed based on the Nine Mile Point commitment to NQA-1 (1983) for design verification activities. This checklist is intended to assist when using the Design Review method of design verification to ensure relevant items are addressed in the verification effort. Each "No" answer will require correction or resolution by the originator of the document being verified prior to full acceptance by the design verifier(s).-

Doc #: H21C096 Lead Design Verifiers M.Berg Name:

Items Addressed with Basis of Review Answer Rve hc Yes No NIA

1. Were the inputs correctly selected ?

x

2. Are assumptions necessary to perform the design activity adequately described and reasonable ? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed activities are completed ?

3. Was an appropriate design method used?

x

4. Were the design inputs correctly incorporated into the design ?

x

5. Isthe design output reasonable compared to design inputs ?

x

6. Are the necessary design input and verification requirements for interfacing organizations specified inthe design documents or insupporting procedures or instructions ? x

ML070110305

Text

References:

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