ML071580365

Calculation H21C-103, Rev 00, U2 CRDA, AST Methodology.

ML071580365
Person / Time
Site:	Nine Mile Point
Issue date:	05/29/2007
From:	Berg M, Metcalf J, Stinson G Engineering Services Co
To:	Office of Nuclear Reactor Regulation
References
H21C-102, Rev 00
Download: ML071580365 (93)

Text

Nine Mile Point Unit 2 Alternative Source Term Calculation H21C-103 "U2 CRDA, AST Methodology"

age 1 (Next la Engineering otal 92 Services ast Attachment 2 Proiect: NINE MILE POINT NUCLEAR STATION Unit (1,2 or O=Both): 2 Discipline: CR Title Calculation No. H21 C-103 U2 CDASTMehdlg 2CRDA, A Methodolog (Sub)system(s) Building IFloor Elev. Index No.

N/A N/A IN/A N/A Originator(s). M. Berg (Design Input Compilation, Case 1 and Appendix C)/ J. Metcalf (Case 2 and Appendices A, B and D), H. Pustulka (Appendix E).

Reviewer(s)/Approver(s) M. Berg (Case 2 and Appendices A, B and D) J. INMP Accptance:

Metcalf (Design Input Compilation, Case I and Appendices C) IdL .i5-/1*- /

Eval., CR, or Rev Description Change No. Prepared By Date Reviewed by Date App Date 00 Initial Release N/A See attached Sig. Sheet 5/29/07 See attached 5/29/07 See attached Sig. 5/29/07 00_niialReeasNAettahe Si._Sheet_7 Sig. Sheet Sheet Computer Output/Microfilm separately filed? (Yes/No/N/A) No Safety Class: (*SRJNSR/Qxx): SR

• If SR, attach or reference the associated Design Verification Report.

Superseded Document(s): 1i-/

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

If (Y/N)

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

References:

Remarks:

Confirmation Required (Yes/No): tj oc Final Issue Status Turnover See Page(s):__P Req'd (Yes/N/A): Y'E!S 10 CFR50.59 Evaluation Number(s): Component ID(s)(As shown in MEL):

Copy of Applicability Determination op6e-ecreen Attached? YeslX No*O D3 N/A 0 *If"No", location of AD/Screen?

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

Engineering Page la Services Next (2)

Title Calculation No.

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ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -21 (Next 3-) j Project: Nine Mile Point NuclearStation Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1:J. Metcalf 5/29/2007 H21C-103 0 Case 2: J. Metcalf 512912007 Case 2: M.Berg 5/29/2007 Ref.

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 AI-A5 0 la 0 B1-B2 0 2 0 C1-C13 0 3 0 D1-D40 0 4 0 El-Ell 0 5 0 Attach 1 0 6 0 Attach 2 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 Total Number of Calculation Pages - - .

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -3 (Next 4)

Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Odginator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5129/2007 H21C-103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 ef.

Table of Contents CALCULATION COVER SHEET ................................................................................................................... I List of Effe ctive Page s.................................................................................................................................... 2 Table of Conte nts ........................................................................................................................................... 3 Purp ose ......................................................... ................................ ................................................................ 4 Summa ry of Res ults ....................................................................................................................................... 5 Meth odolo gy .................................................................................................................................................. 5 As sumptio ns .................................................................................................................................................. 7 Refe re nce s..................................................................................................................................................... 7 Design Input ................................................................................................................................................... 8 Calc ula tion ................................................................................................................................................... 11 Cas e I .......................................................................................................................................................... 11 Case 2-. ........................................................................................................................................................ 16 Conclu s ions ................................................................................................................................................. 18 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 (2Pages)

Appendix C: Steam Line Radiation Monitor Response (13 Pages)

Appendix D: RADTRAD Dose Analysis for Case 2 (40 Pages)

Appendix D-1: Primary Input (.psf) file, Plant Scenerio File, nmp2crda-2pmp"'.psf Appendix D-2: Secondary Input (.nif, .rft, .inp) files Appendix D-2.1: Appendix D-2.1: Nuclide Information File, nmp2.nif Appendix D-2.2: Appendix D-2.2: Release Fraction File, nmp2-crda.rft Appendix D-2.3: Appendix D-2.3: Dose Conversion Factor File, nmp2.inp Appendix D-3: Appendix D-3: Radtrad Output (.o0) file, nmp2crda.2pmp".out (Excerpt)

Appendix E: Check Calculation using STARDOSE for CRDA Dose Analysis, Case 2 (11 Pages)

Appendix E-1: STARDOSE Library File (LIBFILEI.txt)

Appendix E-2: STARDOSE Main Input File for CRDA Case 2 Appendix E-3: STARDOSE Results for CRDA Case 2 (Excerpts)

Attachment 1: Design Verification Report (1Page)

Attachment 2: Design Verification Checklist (1 Page)

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page 4 (Next 5 _)

Project: Nine Mile Point NuclearStation Unit: 2 -Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

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 (MSIVs) o Case 2: Main Condenser not isolated, mechanical vacuum pump in operation.

This analysis includes the impact of a Unit 1 CRDA on the Unit 2 control room, as well as a Unit 2 CRDA on the Unit 1 and the Unit 2 control rooms.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _5 (Next 6)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

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

(rem) (rem) (rem)

EAB 5.68E-01 1.03 6.3 LPZ 7.73E-02 1.17 6.3 U1 CRDA on U2 CR 7.88E-01 <1.61 5.0 U2 CRDA on U1 CR 1.57E-01 <2.31 5.0 U2 CRDA on U2 CR 1.26E+00 2.31 5.0

• Reference I

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,

2. The most limiting person at the inner boundary of the LPZ would not be subjected to radiation exposure resulting in doses in excess 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 = 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to t = 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. 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 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 of the computer code RADTRAD 3.03 [Ref 2] to determine the activity releases, offsite doses, and control room dose. Verification of the RADTRAD runs was performed using the STARDOSE 1.01 computer code [Ref 3] and is documented in Appendix E.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the start of the accident.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page .6 (Next 7_)

Project: Nine Mile Point Nuclear Station Unit: Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 ef.

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. Given a CRDA, in the instance where the transport of activity is much slower than in Case 1 (i.e., 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 operating). This case is analyzed in the following way:

1. Establish a "base" steam line activity concentration (Ci/m 3) with the radionuclide mix corresponding to the CRDA analysis from 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 limit 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 1 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 X/Qs (corresponding to the mechanical vacuum pump exhaust flowpath). Assume the same DFs and end of release from the main condenser (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) as Case 1.

7. Compare the TEDE values obtained in Step 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].

8. Knowing the X/Qs from the Unit 2 release points to the Unit 1 CR and vice versa, demonstrate that doses to the cross-unit CR would be acceptable for Case 2 by comparing the cross-unit X/Qs to the X/Qs used in obtaining the acceptable Case 2 doses for the same-unit CR (that dose may be found in Reference 4 for Unit 1).

As with the calculation of the Unit 1 doses in Reference 4, the dose analysis for both cases for Unit 2 was conducted in full compliance with NRC Regulatory Guide 1.183 [Ref I] using DCFs consistent with References 5 and 6. All Unit 2 input data may be found in Reference 7. For the Case I analysis of the Unit 1 releases to the Unit 2 CR, the input data (except for the X/Qs) may be found in Reference 8.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page j (Next 8 _)

Project: Nine Mile PointNuclear Station Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/2912007 Case 2: M.Berg 5/29/2007 Ref.

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

Justification: The exact leak location for the assumed I% 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 Main Stack (offgas release path). Such an assumption is consistent with the modeling of Unit 1 in Reference 4.

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.

Such an assumption is consistent with the modeling of Unit 1 in Reference 4.

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. Such an assumption is consistent with the modeling of Unit 1 in Reference 4.

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", NUREG/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. H21C096, "U1 CRDA, AST Methodology", 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-93-081, U.S. Environmental Protection Agency, Washington, DC, 1993.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -8 (Next 9)

Project:Nine Mile PointNuclear Station Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5129/2007 Case 2: M.Berg 5/29/2007 Ret.

7. PSAT 3101CF.QA.03, "Design Database for Application of the Revised DBA Source Term to Nine Mile Point Unit 2", Revision 0

8. PSAT 4026CF.QA.03, "Design Database for Application of the Revised DBA Source Term to Nine Mile Point Unit 1", Revision 1 Design Input Design Input Data (Unit 1 input item numbers from Reference 8 given in brackets; Unit 2 input item numbers from Reference 7 given in double brackets):

Unit 1 Power level = 1887 MWt [1.1]

Unit 2 Power Level = 4067 MWt ((1.1))

Unit 1 and Unit 2 Core inventories [1.2] and ((1.2))

Nuclde Ci/MWt Nuclide Ci/MWt Nuclide Ci/MWt Kr83m 3.27E+03 Ru106 1.76E+04 Cs134 7.29E+03 Kr85 3.93E+02 Rhl05 2.84E+04 Cs136 2.28E+03 Kr85m 6.82E+03 Sb127 3.01 E+03 Cs137 4.35E+03 Kr87 1.30E+04 Sb129 8.91E+03 Ba137m 4.12E+03 Kr88 1.83E+04 Te127 3.00E+03 Ba139 4.89+04 Kr89 2.22E+04 Te127m 4.05E+02 Ba140 4.71+04 Rb86 7.29E+01 Te129 8.76E+03 La140 5.12+04 Sr89 2.45E+04 Te129m 1.30E+03 La141 4.45+04 Sr90 3.14E+03 Te131m 3.97E+03 La142 4.29+04 Sr9l 3.10OE+04 Te132 3.85E+04 Ce141 4.47+04 Sr92 3.38E+04 1131 2.71E+04 Ce143 4.11+04 Y90 3.24E+03 1132 3.92E+04 Ce144 3.70+04 Y91 3.18E+04 1133 5.51E+04 Pr143 3.97+04 Y92 3.40E+04 1134 6.03E+04 Nd147 1.80+04 Y93 3.96E+04 1135 5.16E+04 Np239 5.78E+05 Zr95 4.46E+04 Xel 31 m 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 Xe133m 1.63E+03 Pu240 1.89E+01 Mo99 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 Xe137 4.80E+04 Cm242 1.85E+03 Rul05 3.01 E+04 Xe138 4.50E+04 Cm244 1.23E+02

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page 9 (Next 10-)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/2912007

Fef.,I Unit 1 Peaking factor = 1.8 [1.6]

Unit 2 Peaking factor = 1.8 ((1.6))

Unit 1 Total number of fuel assemblies in core = 532 [2.5]

Unit 2 Total number of fuel assemblies in core = 764 ((2.1))

Unit 1 Fuel failure: 850 pins (conservatively based on 8x8 fuel) for a failure fraction of 0.0258 [2.12]

Unit 2 Fuel failure: 770 pins (conservatively based on 8x8 fuel) for a failure fraction of 0.0163 ((2.9))

Unit 1 melt fraction of the failed rods = 0 (no pins are assumed to melt) [2.13]

Unit 2 melt fraction of the failed rods = 0.0077 ((2.10))

Unit 1 and Unit 2 Release fractions for all radionuclide groups [2.14] and ((2.11))

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%

Iodine is partitioned such that 3% of the total released to the environment is organic iodine, and the balance is elemental iodine. [Ref1]

Unit 1 and Unit 2 Leakage rate from main condenser to environs, Case 1 = 1% per day [3.16] and ((3.4))

Unit 1 Control Room volume = 1.35E+05 cuft [3.9]

Unit 2 Control Room volume = 2.02E+05 cuft (53% of 3.81E+05 ft3) ((3.2, 3.3))

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page - 0.

(Nextl 11 Project: Nine Mile Point NuclearStation Unit: 2 Disposition: -

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 2 Case 1:J. Metcalf 5/29/2007 H21 C- 103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.I X/Q 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] and 1.9E-04 U1 N/A N/A N/A N/A

([5.1)) 1.19E-04 U2 EAB stack[ 5.1] and 5.98E-05 UI N/A N/A N/A N/A

((5.1)) 2.96E-05 U2 LPZ ground[ 5.2] and 1.63E-05 U1 1.63E-05 U1 1.10E-05 U1 4.67E-06 Ul 1.37E-06 U1

((5.2)) 1.62E-05 U2 1.62E-05 U2 1.09E-05 U2 4.59E-06 U2 1.33E-06 U2 LPZ stack[ 5.2] and 2.12E-05 U1 1.26E-06 U1 8.40E-07 UI 3.45E-07 UI 1.11E-07 UI

((5.2)) 1.42E-05 U2 1.42E-05 U2 5.41E-07 U2 2.3 1E-07 U2 7.65E-08 U2 U1 accident to U2 Control 1.26E-04 7.73E-05 2.74E-05 2.45E-05 2.23E-05 Room ground (RB) ((5.5))

U2 accident to U1 Control 1.77E-04 1.09E-04 3.92E-05 2.48E-05 1.85E-05 Room ground (RB) ((5.3))

U2 accident to U2 Control 1.09E-03 7.23E-04 2.50E-04 1.92E-04 1.47E-04 Room ground (RB) ((5.5))

U1 accident to U2 Control 1.31E-04 9.42E-05 3.59E-05 3.01E-05 2.63E-05 Room ground (TB) ((5.))

U2 accident to U1 Control 1.90E-04 1.37E-04 4.93E-05 3.12E-05 2.56E-05 Room ground (TB) ((5.3))

U2 accident to U2 Control 1.47E-03 9.74E-04 3.63E-04 2.45E-04 1.90E-04 Room ground (TB) ((5.5))

Ul accident to U2 Control 1.1OE-04 6.16E-05 2.3 1E-05 1.85E-05 1.57E-05 Room stack ((5.5))

U2 accident to Ul Control 4.18E-05 2.30E-05 8.94E-06 5.62E-06 4.31E-06 Room stack ((5.3))

U2 accident to U2 Control 8.03E-05 4.48E-05 1.68E-05 1.20E-05 8.83E-06 Room stack ((5.5)) _. _

• For the LPZ, value is based on the worst 4 hours Control Room breathing rates in m3/s [5.4] and ((5.6))

0-30 days 3.5E-4 EAB & LPZ breathing rates in m3/s [ 5.4] and ((5.6))

0-8 hr 3.5E-4 1-4 days 1.8E-4 4-30 days 2.3E-4 Control Room occupancy factors [ 5.5] and ((5.7))

0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 1-4 days 0.6 4-30 days 0.4

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Pagej 11 (Next 12-)

Project:Nine Mile Point Nuclear Station Unit: Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/2912007 H21C-103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

Unit 2 Main Condenser Mechanical Vacuum Pump volumetric flowrate: 5000 cfmn ((3.5))

Unit 2 Main Condenser volume: 97,000 ft3 ((3.7))

Main Steam Line Radiation Monitor Set Point: 1800rnR ((7.3))

(basis to trip Mechanical Vacuum Pump)

Calculation Case 1 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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 1 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 failure fraction multiplied by the 1% per day release.

DF (Row 7)

DF 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: 1/(10%*10%)=100. 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 (= RFeff) (column 3):

The group specific release fraction from the gap and melted fuel to the coolant is used to scale the nuclides using the following formula:

RFeff [RFgap + fmeit *RFmelt]*specfrac/DF correction

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -12 (Next 13 _)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

where RFcff = effective release fraction RFgap = release fraction from gap RFmett = release fraction from melted fuel fmet = fraction of fuel melted specfrac = species fraction (=.03 organic iodines, 0.97 elemental iodine, 1.0 othersO Unit 1 DF Soecfrac I RF,. R.F-,,It correction RF~

1 RFeff Noble Gas 1.0 0.1 1.0 0 0.1 Iodine 0.97 0.1 0.5 0 0.097 Iodine org* 0.03 0.1 0.5 0 100 3.OE-05 Cs, Rb 1.0 0.12 0.25 0 1 0.12 Unit 2 DF specfrac RFgap RFmelt fmelt correction RFeff Noble Gas 1 0.1 1 0.0077 1 0.1077 Iodine 0.97 .0.1 0.5 0.0077 1 0.10073 Iodine org* 0.03 0.1 0.5 0.0077 100 3.116E-05 Cs, Rb 1 0.12 0.25 0.0077 1 0.121925

• Recognizing that the elemental iodine is treated with a DF of 100, the scaling factor for organic iodine is modified by (1/100).

The results of this calculation can be seen in Table 2 below.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page 3 13 (Next 14 )

Project: Nine Mile Point Nuclear Station Unit: _2- Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 5(29(2007 Case 2: M.Berg 5/29/2007 Rif Table 2a: CRDA Case 1 Dose Analysis Results U1 CRDAJU2 Control Room NMP1 CRDA/U2 CR EAB LPZ CR Dispersion (X/Qs) = 1.90E-04 1.63E-05 1.31E-03 sec/m3 CR Vol = 202000 ft3 w/ finite volume gamma correction 0.0529555 Scaling Factor 1 = 1887 MW(t)

Scaling Factor 2 = 1.8 Peaking Factor Scaling Factor 3 = 2.60E-04 (0.026 core x 0.01 release)

DF for Elemental I = 100 DF for Alkali Metals = 1.00E+04 Nuclide- WB CEDE TEDE CR EAB 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 Ci-sec Kr83m 3.27E+03 0.1 5.6E-06 0 5.55E-06 2.939E-07 3.05E-07 2.61E-08 1.11E-07 Kr85m 6.82E+03 0.1 0.0277 0 0.0277 0.0014669 3.17E-03 2.72E-04 1.16E-O0 Kr85 3.93E+02 0.1 0.00044 0 0.00044 2.33E-05 2.90E-06 2.49E-07 1.06E-0(

Kr87 1.30E+04 0.1 0.152 0 0.152 0.0080492 3.32E-02 2.84E-03 1.2 1E-0, Kr88 1.83E+04 0.1 0.501 8.36E+01 0.53026 0.0557907 1.63E-01 1.40E-02 1.18E-0]

Kr89 2.22E+04 0.1 0.323 0 0.323 0.0171046 1.20E-01 1.03E-02 4.39E-0, Xel3lm 3.04E+02 0.1 0.00144 0 0.00144 7.626E-05 7.35E-06 6.30E-07 2.68E-O(

Xel33m 1.63E+03 0.1 0.00507 0 0.00507 0.0002685 1.39E-04 1.19E-05 5.06E-0f Xe133 5.27E+04 0.1 0.00577 0 0.00577 0.0003056 5.1OE-03 4.38E-04 1.86E-0; Xel35m 1.09E+04 0.1 0.0755 0 0.0755 0.0039981 1.38E-02 1.18E-03 5.04E-0!

Xe135 1.91E+04 0.1 0.044 0 0.044 0.00233 1.41E-02 1.21E-03 5.15E-0.

Xe137 4.80E+04 0.1 0.0303 0 0.0303 0.0016046 2.44E-02 2.09E-03 8.9 1E-0.

Xe138 4.50E+04 0.1 0.213 0 0.213 0.0112795 1.61E-01 1.38E-02 5.87E-0, I131Org 2.71E+04 0.00003 0.0673 3.29E+04 11.5823 11.518564 1.58E-03 1,36E-04 1.08E-0, 11320rg 3.92E+04 0.00003 0.414 3.81E+02 0.54735 0.1552736 1.08E-04 9.27E-06 2.11E-0L 11330rg 5.51EE+04 0.00003 0.109 5.85E+03 2.1565 2.0532721 5.98E-04 5.13E-05 3.93E-0.

11340rg 6.03E+04 0.00003 0.481 1.31 E+02 5.27E-01 0.0713216 1.60E-04 1.37E-05 1.49E-0O 11350rg 5.16E+04 0.00003 0.307 1.23E+03 0.7375 0.4467573 1.92E-04 1.64E-05 8.00E-0z I131Elem 2.71E+04 0.097 0.0673 3.29E+04 11.5823 11.518564 5.11E-02 4.38E-03 3.50E-0]

I132Elem 3.92E+04 0.097 0.414 3.81E+02 0.54735 0.1552736 3.49E-03 3.OOE-04 6.83E-02 I133Elem 5.51E+04 0.097 0.109 5.85E+03 2.1565 2.0532721 1.93E-02 1.66E-03 1.27E-0 ]

l134Elem 6.03E+04 0.097 0.481 1.3 IE+02 0.52685 0.0713216 5.17E-03 4.44E-04 4.83E-O' I135Elem 5.16E+04 0.097 0.307 1.23E+03 7.38E-01 0.4467573 6.19E-03 5.3 1E-04 2.59E-0, Rb86 7.29E+01 0.12 0.0178 6.62E+03 2.3348 2.3179426 3.43E-07 2.94E-08 2.35E-0(

Cs134 7.29E+03 0.12 0.28 4.63E+04 16.485 16.219828 2.42E-04 2.08E-05 1.64E-0.

Cs136 2.28E+03 0.12 0.392 7.33E+03 2.9575 2.5862585 1.36E-05 1.16E-06 8.19E-0' Cs137 4.35E+03 0.12 0.101 3.19E+04 11.266 11.170349 9.87E-05 8.47E-06 6.75E-0z Cs138 0 0.12 0.4255 1.15E+02 0.465904 0.0629365 0.OOE+00 0.OOE+00 0.OOE+0(

Tot TEDE = 6.26E-01 5.37E-02 7.88E-01

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page 414 (Next 15_)

Project: Nine Mile Point Nuclear Station Unit: Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21C-1 03 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 R:ef.

Table 2b: CRDA Case 1 Dose Analysis Results U2 CRDA/U1 Control Room NMP2 CRDA/U1 CR EAB LPZ CR Dispersion (X/Qs) = 1.19E-04 I.62E-05 1.90E-04 sec/m3 CR Vol = 135000 ft3 w/ finite volume gamma correction = 0.046212004 Scaling Factor 1 = 4067 MW(t)

Scaling Factor 2 = 1.8 Peaking Factor Scaling Factor 3 = 1.63E-04 (0.0163 core x 0.01 release)

DF for Elemental I 100 DF for Alkali Metals = 1.00E+04 Nuclide- WB CEDE TEDE CR EAB LPZ CR Source: Specific DCF DCF DCF DCF TEDE TEDE TEDE Units >> Ci/MW(t) Scaling rern-m3 rem/Ci rem-m3 rem-m3 rem rem rem Nuclide Factor Ci-sec Ci-sec Ci-sec Kr83m 3.27E+03 0.1077 5.6E-06 0 5.55E-06 2.56477E-07 2.78E-07 3.78E-08 2.05E-08 Kr85m 6.82E+03 0.1077 0.0277 0 0.0277 0.001280073 2.89E-03 3.93E-04 2.13E-04 Kr85 3.93E+02 0.1077 0.00044 0 0.00044 2.03333E-05 2.64E-06 3.60E-07 1.95E-07 Kr87 1.30E+04 0.1077 0.152 0 0.152 0.007024225 3.02E-02 4.11E-03 2.23E-03 Kr88 1.83E+04 0.1077 0.501 8.36E+01 0.53026 0.052412214 1.48E-01 2.02E-02 2.34E-02 Kr89 2.22E+04 0.1077 0.323 0 0.323 0.014926477 1.1OE-01 1.49E-02 8.09E-03 Xel3lm 3.04E+02 0.1077 0.00144 0 0.00144 6.65453E-05 6.69E-06 9.11E-07 4.94E-07 Xel33m 1.63E+03 0.1077 0.00507 0 0.00507 0.000234295 1.26E-04 1.72E-05 9.33E-06 Xe133 5.27E+04 0.1077 0.00577 0 0.00577 0.000266643 -4.65E-03 6.33E-04 3.43E-04 Xel35m 1.09E+04 0.1077 0.0755 0 0.0755 0.003489006 1.26E-02 1.71E-03 9.29E-04 Xe135 1.91E+04 0.1077 0.044 0 0.044 0.002033328 1.29E-02 1.75E-03 9.48E-04 Xe137 4.80E+04 0.1077 0.0303 0 0.0303 0.001400224 2.22E-02 3.03E-03 1.64E-03 Xe138 4.50E+04 0.1077 0.213 0 0.213 0.009843157 1.47E-01 2.OOE-02 1.08E-02 I131Org 2.71EE+04 3.116E-05 0.0673 3.29E+04 11.5823 11.51811007 1.39E-03 1.89E-04 2.20E-03 11320rg 3.92E+04 3.116E-05 0.414 3.81E+02 0.54735 0.15248177 9.49E-05 1.29E-05 4.22E-05 11330rg 5.5I1EE+04 3.116E-05 0.109 5.85E+03 2.1565 2.052537108 5.26E-04 7.16E-05 7.99E-04 11340rg 6.03E+04 3.116E-05 0.481 1.3 1E+02 5.27E-01 0.068077974 1.41E-04 1.91E-05 2.90E-05 11350rg 5.16E+04 3.116E-05 0.307 1.23E+03 0.7375 0.444687085 1.68E-04 2.29E-05 1.62E-04 I131Elem 2.71E+04 0.10073 0.0673 3.29E+04 11.5823 11.51811007 4.49E-02 6.11E-03 7.13E-02 I132Elem 3.92E+04 0.10073 0.414 3.81E+02 0.54735 0.15248177 3.07E-03 4.18E-04 1.37E-03 I133Elem 5.51E+04 0.10073 0.109 5.85E+03 2.1565 2.052537108 1.70E-02 2.31E-03 2.58E-02 I134Elem 6.03E+04 0.10073 0.481 1.31E+02 0.52685 0.068077974 4.54E-03 6.19E-04 9.38E-04 I135Elem 5.16E+04 0.10073 0.307 1.23E+03 7.38E-01 0.444687085 5.44E-03 7.41E-04 5.24E-03 Rb86 7.29E+01 0.12193 0.0178 6.62E+03 2.3348 2.317822574 2.95E-07 4.01E-08 4,67E-07 Cs134 7.29E+03 0.12193 0.28 4.63E+04 16.485 16,21793936 2.08E-04 2.83E-05 3.27E-04 Cs136 2.28E+03 0.12193 0.392 7.33E+03 2.9575 2.583615106 1.17E-05 1.59E-06 1.63E-05 Cs137 4.35E+03 0.12193 0.101 3.19E+04 11.266 11.16966741 8.48E-05 1.16E-05 1.34E-04 Cs138 0 0.12193 0.4255 1.15E+02 0.465904 0.060067208 0.OOE+00 0.OOE+00 0.OOE+00 Tot TEDE = 5.68E-01 7.73E-02 1.57E-01

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -5.....

(Next _16 15 Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5129/2007 H21 C-103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 ef. I Table 2c: CRDA Case 1 Dose Analysis Results U2 CRDA/U2 Control Room NMP2 CRDA/ U2 CR EAB LPZ CR Dispersion (X/Qs) = 1.19E-04 1.62E-05 1.47E-03 sec/m3 CR Vol = 202000 ft3 w/ finite volume gamma correction 0.052955 Scaling Factor I = 4067 MW(t)

Scaling Factor 2 = 1.8 Peaking Factor Scaling Factor 3 = 1.63E-04 (0.0163 core x 0.01 release)

DF for Elemental I = 100 DF for Alkali Metals = 1.00E+04 Nuclide- WB CEDE TEDE CR EAB 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 Ci-sec Kr83m 3.27E+03 0.1077 5.6E-06 0 5.55E-06 2.94E-07 2.78E-07 3.78E-08 1.82E-0"*

Kr85m 6.82E+03 0.1077 0.0277 0 0.0277 0.001467 2.89E-03 3.93E-04 1.89E Kr85 3.93E+02 0.1077 0.00044 0 0.00044 2.33E-05 2.64E-06 3.60E-07 1.73E-0(

Kr87 1.30E+04 0.1077 0.152 0 0.152 0.008049 3.02E-02 4.11E-03 1.98E-0:

Kr88 1.83E+04 0.1077 0.501 8.36E+01 0.53026 0.055791 1.48E-01 2.02E-02 1.93E-01 Kr89 2.22E+04 0.1077 0.323 0 0.323 0.017105 1.1OE-01 1.49E-02 7.17E-0:

Xel3lm 3.04E+02 0.1077 0.00144 0 0.00144 7.63E-05 6.69E-06 9.11E-07 4.38E-0(

Xel33m 1.63E+03 0.1077 0.00507 0 0.00507 0.000268 1.26E-04 1.72E-05 8.27E-0, Xe133 5.27E+04 0.1077 0.00577 0 0.00577 0.000306 4.65E-03 6.33E-04 3.04E-0-1 Xel35m 1.09E+04 0.1077 0.0755 0 0.0755 0.003998 1.26E-02 1.71E-03 8.23E-02 Xe135 1.91E+04 0.1077 0.044 0 0.044 0.00233 1.29E-02 1.75E-03 8.41 E-02 Xe137 4.80E+04 0.1077 0.0303 0 0.0303 0.001605 2.22E-02 3.03E-03 1.45E-0, Xe138 4.50E+04 0.1077 0.213 0 0.213 0.01128 1.47E-01 2.00E-02 9.59E-0:

I131Org 2.71E+04 3.116E-05 0.0673 3.29E+04 11.5823 11.51856 1.39E-03 1.89E-04 1.71E-0, 11320rg 3.92E+04 3.116E-05 0.414 3.81 E+02 0.54735 0.155274 9.49E-05 1.29E-05 3.33E-04 11330rg 5.51E+04 3.116E-05 0.109 5.85E+03 2.1565 2.053272 5.26E-04 7.16E-05 6.18E-02 11340rg 6.03E+04 3.116E-05 0.481 1.31 E+02 5.27E-01 0.071322 1.41E-04 1.91E-05 2.35E-04 11350rg 5.16E+04 3.116E-05 0.307 1.23E+03 0.7375 0.446757 1.68E-04 2.29E-05 1.26E-02 Il31Elem 2.71 E+04 0.10073 0.0673 3.29E+04 11.5823 11.51856 4.49E-02 6.11E-03 5.52E-01 I132Elem 3.92E+04 0.10073 0.414 3.8iE+02 0.54735 0.155274 3.07E-03 4.18E-04 1.08E-02 I133Elem 5.51E+04 0.10073 0.109 5.85E+03 2.1565 2.053272 1.70E-02 2.3 1E-03 2.OOE-01 I134Elem 6.03E+04 0.10073 0.481 1.3 1E+02 0.52685 0.071322 4.54E-03 6.19E-04 7.60E-03 I135Elem 5.16E+04 0.10073 0.307 1.23E+03 7.38E-01 0.446757 5,44E-03 7.41E-04 4.07E-02 Rb86 7.29E+01 0.12193 0.0178 6.62E+03 2.3348 2.317943 2.95E-07 4.01E-08 3.6 1E-0O Cs134 7.29E+03 0.12193 0.28 4.63E+04 16.485 16.21983 2.08E-04 2.83E-05 2.53E-03 Cs136 2.28E+03 0.12193 0.392 7.33E+03 2.9575 2.586259 1.17E-05 1.59E-06 1.26E-04 Cs137 4.35E+03 0.12193 0.101 3.19E+04 11.266 11.17035 8.48E-05 1.16E-05 1.04E-03 Cs138 0 0.12193 0.4255 1.15E+02 0.465904 0.062937 0.OOE+00 0.OOE+00 0.OOE+0(

Tot TEDE 5.68E-01 7.73E-02 1.26E+OC

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -16.

(Next 17_)

Project.Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

Case 2-Step 1. Establish 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 6.15E6 Ci. The reference concentration is calculated in Appendix C based on this activity being compressed into a single, 32 foot length of steam line with a 25.33" ID. The result is 1.94 Ci/cc or 1.94E6 Ci/m3 .

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 0.0595 R/hr per Ci/m 3 of the CRDA release.

Step 3 - Activity Concentration Producing Safety Limit Dose Rate Since the safety limit of the radiation monitor is 1800 mrR/hr (Item 7.3 of Reference 7) or -1.8 R/hr, the 0.0595 R/hr per Ci/m3 value means that aconcentration greater than 1.8/0.0595 = 30.25 Ci/m3 would be sufficient to terminate mechanical vacuum pump operation. Therefore, a concentration of 30.25 Ci/m 3 = 0.857 Ci/ft3 is assumed in the dose analysis.

Step 4 - Source Volume Needed to Contain Source The source is 6.15E6 Ci at a concentration of 0.857 Ci/ft3 . The volume must effectively be 7.17E6 ft3.

Step 5 - Maximum Steam Volumetric Flow for Continued Mechanical Vacuum Pump Operation The maximum reactor power and minimum pressure that would be consistent with mechanical vacuum pump operation would be 5% and.300 psig, respectively. These conditions are taken from the assessment done for Unit 1 described in Attachment 3 to Reference 8. The corresponding steam flow for Unit 2 is based on the rated power of 3467 MWt multiplied by 1.15 in anticipation of a 15% power uprate.

Applying the identical approach to that of Attachment 3 to Reference 8, the resulting steam flow is 5.99E5 Ibm/hr. The corresponding volumetric flow (with saturated steam specific volume at 300 psig 1.47 ft3/lbm) is:

Steam volumetric flow = 5.99E5 Ibm/hr x 1.47 ft3/lbm = 8.805E5 cfh = 14680 cfm.

Step 6 - Perform Dose Analysis with RADTRAD and STARDOSE For an activity concentration of 0.857 Ci/ft3 and a steam volumetric flow of 14680 cfm, the activity release rate to the main condenser is:

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -7 (Next 18-)

Project:Nine Mile PointNuclear Station Unit: Disposition:

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007 Case 1: J. Metcalf 5/29/2007 H21 C-1 03 0 Case 2: J. Metcalf 512912007 Case 2: M.Berg 5129/2007 Ref.

Activity release rate to the main condenser = 14680 cfm x 0.857 Ci/ft3 = 1.258E4 Ci/min.

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

Time to release 99% of activity = 4.6 x 7.17E6 ft3/14680 cfm = 2247 min or -37 hours.

The main condenser has a volume of 97,000 ft3 and an exhaust rate using the mechanical vacuum pump of 5000 cfm. (Item 3.5 of Reference 7). 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 7.17E6 ft3. This volume is then emptied at a rate of 14680 cfm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The main condenser has a volume of 97,000 ft3, (Item 3.7 of Reference 7), and this volume is emptied at a rate of 5000 cfmn, also for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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):

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 5010 Ci of Kr85 released according to Appendix B, one can expect the Kr85 activity in the main condenser for the actual dose analysis to peak at about 80 minutes with a level of about 0.035 x 5010 = 175 Ci.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page j18-(Next _A1 _

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Design Input Compilation and Reviewer/Date Calculation No. Revision Case 1: M.Berg 5/29/2007, Case 1: J. Metcalf 5/29/2007 H21 C-103 0 Case 2: J. Metcalf 5/29/2007 Case 2: M.Berg 5/29/2007 Ref.

The actual result from the STARDOSE analysis at t = 1.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> is 174 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 -30 minutes to -150 minutes when the activity in the main condenser is the highest. The actual result from the RADTRAD analysis presented in Appendix D is that the worst two hours begins at -20 minutes; this is likely the result of the decay of short-lived radionuclides.

The control room model is similar to that in Case 1. The same steam line and main condenser DFs 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, so the duration of release is the same as Case 1. As can be seen from the above figure, however, there is very little activity remaining in the main condenser at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any case.

The Unit 2 power level of 4067 MWt is increased to 7321 MWt for use in RADTRAD and STARDOSE. In this way, the nuclide inventories used in the "standard" RADTRAD and STARDOSE library files (Reference 7, 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 References 7.and 8.

The input, library, and output files for RADTRAD are presented in Appendix D. The input, library, and output files for STARDOSE 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 BWR 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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.

fZ)

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page A1 (NextA22 )

Project-Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 M.Berg 5/29/2007 H21C-103 0 Ref.

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 A/t. 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 form 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 m 3/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 TID.INP and FGR60.INP 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.

2V ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page A2 (Next _A3 -)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 M.Berg 5/29/2007 H21C-103 0 Ref.

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 "NMP1 MSLB".

In the second row may be found the EAB, LPZ, and control room X/Qs in units of seconds/m 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 1 (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 specific activity in the 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 annotate 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 1-131 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 TID.INP and FGR60.INP 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 FGR60.INP have been multiplied by the same 3.7E12 to convert Sv/Bq to remr/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

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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 immersion DCF and the inhalation DCF times the assumed breathing rate of 3.5E-4 m 3/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:

3 8

=DDeOE, V--

OOEf~

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 EAB dose, the product of Columns 2, 3, and 6, the three general scaling factors, and the EAB X/Q. Note that if a release of the activity, A, in Column 2 occurs over time, t, the release rate is A/t 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 EAB dose is summed for all radionuclides in Column 1. Note that in calculating the EAB 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 X/Q to the EAB 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 EAB 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 EAB 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: 2 Disposition:

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Spreadsheet for Simplified Dose Evaluation TITLE EAB LPZ CR Dispersion (X/Qs) = x.xxE-xx x.xxE-xx x.xxE-xx sec/m3 CR Vol = 1.20E+09 ft3 w/ finite volume gamma correction 0.999 Scaling Factor I = I Scaling Factor 2 = 1 Scaling Factor 3 = I DF for Elemental I I DF for Alkali Metals I Nuclide- WB CEDE TEDE CR EAB LPZ CR Source: Specific DCF DCF DCF DCF TEDE TEDE TEDE Units >> Scaling rem-m3 rem/Ci rem-m3 rem-m3 rem rem rem Nuclide Factor Ci-sec Ci-sec Ci-sec Kr83m 0 1 5.55E-06 0 5.55E-06 5.54E-06 0.OOE+00 0.OOE+00 0.OOE+00 Kr85m 0 1 0.0277 0 0.0277 0.027666 0.00E+00 0.OOE+00 0.OOE+00

]Kr85 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.OOE+00 0.00E+00 Kr88 0 1 0.501 8.36E÷01 0.53026 0.529643 0.OOE+00 0.OOE+00 0.00E+00 Kr89 0 1 0.323 0 0.323 0.322603 0.OOE+00 0.OOE+00 0.OOE+00 Xel3lm 0 1 0.00144 0 0.00144 0.001438 0.OOE+00 0.OOE+00 0.OOE+00 Xe133m 0 1 0.00507 0 0.00507 0.005064 0.OOE+00 0.OOE+00 0.OOE+00 Xe133 0 1 0.00577 0 0.00577 0.005763 0.OOE+00 0.OOE+00 0.OOE+00 Xe135m 0 1 0.0755 0 0.0755 0.075407 0.OOE+00 0.OOE+00 0.OOE+00 Xe135 0 1 0.044 0 0.044 0.043946 0.OOE+00 0.OOE+00 0.OOE+00 Xe137 0 1 0.0303 0 0.0303 0.030263 0.OOE+00 0.OOE+00 0.00E+00 Xe138 0 1 0.213 0 0.213 0.212738 0.OOE+00 0.OOE+00 0.00E+00 I131Org 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 1.31E+02 5.27E-01 0.526258 0.OOE+00 0.OOE+00 0.OOE+00 I135Org 0 1 0.307 1.23E+03 0.7375 0.737122 0.OOE+00 0.OOE+00 0.OOE+00 I131Elem 0 1 0.0673 3.29E+04 11.5823 11.58222 0.OOE+00 0.OOE+00 0.OOE+00 I132Elem 0 1 0.414 3.81EE+02 0.54735 0.546841 0.OOE+00 0.OOE+00 0.OOE+00 1133Elem 0 1 0.109 5.85E+03 2.1565 2.156366 0.OOE+00 0.OOE+00 0.OOE+00 I134EIem 0 1 0.481 1.31E+02 0.52685 0.526258 0.00E+00 0.00E+00 0.OOE+00 I135EIem 0 1 0.307 1.23E+03 7.38E-01 0.737122 0.00E+00 0.OOE+00 0.OOE+00 Rb86 0 1 0.0178 6.62E+03 2.3348 2.334778 0.OOE+00 0.OOE+00 0.OOE+00 Cs134 0 1 0.28 4.63E+04 16.485 16.48466 0.OOE+00 0.OOE+00 0.OOE+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+00 Cs138 0 1 0.4255 1.15E+02 0.465904 0.46538 0.OOE+00 0.OOE+00 0.OOE+00 Total TEDE O.OOE+00 O.OOE+00 O.OOE+00

-a

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Ref, References A-I Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000 A-2 K.F. Eckerman et al., "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-93-081, Environmental Protection Agency, 1993 A-4 NUREG/CR-6604, "RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", December 1997

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Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 M.Berg 5/29/2007 H21 C-1 03 0 Ref.

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 Unit 2 CRDA with a peaking factor of 1.8, a power level of 4067 MWt, and release fractions from the main body of the calculation. This analysis only applies to a Unit 2 accident. The Unit I MSL radiation monitor calculation is found in the Unit 1 CRDA 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 (1.63%) by the group specific effective release fraction from the gap and fuel melt to the coolant. The effective release fraction was determined in the main body of the text. 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:

(1.63%)*(0.97) [0.1"(l-0.0077)+0.5*0.0077)] = 1.6298E-03 In the third column, the Ci/MW(t) are the core inventories taken from Item 1.2 of Reference 7 of the main body.

These are multiplied by the power level of 4067 MWt and the peaking factor of 1.8 to obtain the fourth column. The total of the fourth column total is 6.15E+06 Ci. The last column is the percentage of the total Ci released for each radionuclide considered.

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Unit 2 Activities Released for CRDA:

Nuclide Rel Fract Ci/MWt Ci Percentage Kr83m 1.74E-03 3270 4.17E+04 4.17E+04 Kr85m 1.74E-03 6820 8.70E+04 8.70E+04 Kr85 1,74E-03 393 5.01E+03 5.01 E+03 Kr87 1.74E-03 13000 1.66E+05 1.66E+05 Kr88 1.74E-03 18300 2.33E+05 2.33E+05 Kr89 1.74E-03 22200 2.83E+05 2.83E+05 Xe131m 1.74E-03 304 3.88E+03 3.88E+03 Xe133m 1.74E-03 1630 2.08E+04 2.08E+04 Xe133 1.74E-03 52700 6.72E+05 6.72E+05 Xe135m 1.74E-03 10900 1.39E+05 1.39E+05 Xe135 1.74E-03 19100 2.44E+05 2.44E+05 Xe137 1.74E-03 48000 6.12E+05 6.12E+05 Xe138 1.74E-03 45000 5.74E+05 5.74E+05 1131Org 5.04E-05 27100 1.00E+04 1.OOE+04 11320rg 5.04E-05 39200 1.45E+04 1.45E+04 11330rg 5.04E-05 55100 2.03E+04 2.03E+04 11340rg 5.04E-05 60300 2.23E+04 2.23E+04 11350rg 5.04E-05 51600 1.90E+04 1.90E+04 1131Elem 1.63E-03 27100 3.23E+05 3.23E+05 1132Elem 1.63E-03 39200 4.68E+05 4.68E+05 1133Elem 1.63E-03 55100 6.57E+05 6.57E+05 1134Elem 1.63E-03 60300 7.19E+05 7.19E+05 1135Elem 1.63E-03 51600 6.16E+05 6.16E+05 Rb86 1.97E-03 72.9 1.05E+03 1.05E+03 Cs134 1.97E-03 7290 1.05E+05 1.05E+05 Cs136 1.97E-03 2280 3.29E+04 3.29E+04 Cs137 1.97E-03 4350 6.28E+04 6.28E+04 Total 6.15E+06 100.00%

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Appendix C: Steam Line Radiation Monitor Response The Main Steam Radiation Monitor response to radioisotopes in the Main Steam Lines is investigated here. The MicroShield 7 model of the Main Steam Lines is based on information found in Reference C-1 (relevant pages attached to ref. C2). The model has been baselined against the results of Reference C-1. A CRDA source spectra is then used in the MicroShield 7 model of the Main Steam Lines to predict the (mRnhr)/(uCi/cc) response (calibration factor) for the Main Steam Line Radiation Monitor exposed to the CRDA activity mix.

Base Geometry (Normal Source)

The NMP Unit 2 Main Steam Radiation Monitors have the following configuration relative to the Main Steam Lines _(al details and dimensions taken from Reference C-2):

Jet Containment Impin Line # 028-3-4 ement wall Line #028-1-4

• 1 *2 eactor CL

" *3 *4 Line #028-7-4

, Line #028-5-4 ~o *~=monitor Z

-- -- - -I . . . . . . . .. .. . . . . . . . . . . .. .. . . .. . .. - - - - - - - - - -- - - - -

The Main Steam Lines are 28" except for the ends at the containment wall (opposite end from the radiation monitors), which are 26". The 26" lines will be assumed to be 28" for the purposes of this calculation, as this will result in negligibly higher monitor responses.

OD = 28.006" therefore IR = 28.006"/2-1.339) = 12.664" Clad thickness = 1.339" Line length = 32' (inside ofjet impingement wall to containment wall and includes the 26" lines Each radiation monitor is encased in a 6" Sch 40 pipe with OD=6.625", ID=6.065", clad =

(6.625-6.025)/2 = 0.28", sealed at the end with a 0.5" plate. To model this configuration, a 1/2" shield is placed in between the source and the detector locations.

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Normal Steam Density: 0.036 g/cc (saturation at operating pressure of 1003 psia - refer to Reference C-1)

CRDA Steam Density: 0.011 g/cc (saturation at assumed CRDA pressure of 300 psig - see main body of calculation)

Due to the size of the line, the default Microshield source meshing is increased to a 20x20x50 mesh.

A single Main Steam Line is modeled with four dose points representing the location of each detector relative to all four of the lines.

Dose Point Locations (taken from Reference C- 1 and C-2, units in cm):

1: (370.84, 916.94, 190.66) 2: (325.12, 916.94, 190.66) 3: (190.66, 916.94, 30.48)*

4: (76.2, 916.94, 190.66)

• note: Dose Point #3 x and z coordinates were intentionally swapped from the Reference C-1 standard due to MicroShield 7 modeling constraints. MicroShield 7 does not allow dose points to be "behind" the shield (which is the case with the original coordinates). Due to symmetry, the coordinates may be swapped. This is not strictly correct with a shield in place, since the angle of the ray tracing through the shield will be different, however several test cases showed that there is not a large difference in results by swapping the coordinates.

The default source meshing is-expanded to a 20x20x50 mesh since the source is so large.

Baseline Validation of the Geometry From Reference C-I (relevant pages attached to Reference C-2), the N-16 source of 3.6 gCi/cc is used. Using the same source in the above model yields the following results:

Normal Operation Baseline of Model dose pt original MicroShield  % diff 1 0.174 0.1726 -0.8046 2 0.196 0.1935 -1.27551 3 0.387 0.4563 17.90698 4 0.424 0.2587 -38.9858 total 1.181 1.0811 -8.45893 The Dose Points 1 and 2 in the MicroShield model are almost exactly the same as the baseline

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model. The detectors 3 and 4 are not as good because the original model has a more complex arrangement around the detector not possible to model in MicroShield 7. However, overall, there is less than a 7% error in the MicroShield 7 model, therefore the modeling is good enough for the purposes of this calculation. In particular, the model underpredicts the response, which is conservative in terms of determining the Calibration Factor.

Calibration Factor Using the following source term from Appendix B:

Ci released Kr83m 4.17E+04 Kr85m 8.70E+04 Kr85 5.01 E+03 Kr87 1.66E+05 Kr88 2.33E+05 Kr89 2.83E+05 Xe131m 3.88E+03 Xe133m 2.08E+04 Xe133 6.72E+05 Xe135m 1.39E+05 Xe135 2.44E+05 Xe137 6.12E+05 Xe138 5.74E+05 1131 3.33E+05 1132 4.82E+05 1133 6.78E+05 1134 7.42E+05 1135 6.35E+05 Rb86 1.05E+03 Cs134 1.05E+05 Cs136 3.29E+04 Cs137 6.28E+04 sum 6.15E+06 MicroShield results using Normal Model with CRDA source dose point mR/hr I 1.929E+07 2 2.146E+07 3 5.230E+07 4 2.235E+07 sum 1.154E+08

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

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From the MicroShield output, the volume is 3.17E6 cc The calibration factor is then:

4 lines * (1.154E8 mR/hr/ 1000 R/mR) = 5.95E-2 (R/hr)/(pCi/cc) = (5.95E-2 R/hr)/(Ci/m 3) 4 * (6.15E6 Ci*IE6 LCiICi) / 3.17E6 cc where the Ci/mr3 must be assumed to exist in all four steam lines in the dose analysis (i.e., it is multiplied by the total steam flow rate to obtain the activity release per unit time).

References C-1. Calculation 12177-PR(C)-28-W RO "Dose Rate at the Rad. Monitors (2MSS-RE46A,B,C&D) and Dose Rate Fall-off from the Main Steam Line In the Main Steam Tunnel During Normal Operation and Post-LOCA in order to Address GE Doc. NEDO-30324 Concerns" C-2. PSAT 3101CF.QA.03, "Design Database for Application of the Revised DBA Source Term to Nine Mile Point Unit 2", Revision 0 The following pages contain the output of the Microshield calculations:

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Project: Nine Mile Point Nuclear Station Unit: Disposition: __

Oginator/Date Reviewer/Date Calculation No. Rei o M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0 IRef.I -I Microshield 7.02 Output Reference/Baseline Main Steam Line Calculation Using N-16 Source MicroShield 7.02 Polestar Applied Technology (06-MSD-7..00-11 10) I DaTe re Checked filename Run Date Run Time Duration ref NMP U2 Main Steam normal.ms7 May 24, 2007 6:3 1:14 PM 00:00:03 Project I.nfo Case

Title:

Nine Mile Point U2 Descriotion Main Steam Line: normal source, reference Geomet:,, 7 - Cylinder Volume - Side Shields Source Dimensions Height 975-36 cm (32,3 f (

Radius32-167 cm (1 Ift, 0.7 in)

Dose Points A X Y Z 370-84 __20cmin)(12 ft 916-94 1.0cmi (30

) ft 190.66 cm (6 ft 3 .1in)

=12 325-12 cm(10 ft 916.94 cm (30it, 190.66 cm (6ft 8.0 in)

'- 1.0 in) 3 .1 in) X I31 9 .66 cm (6 ft 3 .1 9 16 .9 4 cm . ,(3 0 ft

_ i*? , 04 m 1f t1.0 inI 76-2 cm (2 ft 6.0 916-94 cm (30 ft, 190.66 cm (6 ft, in ) 1.0 in", , 3.1 in)

Shields Shield N Dimension Material Densi&,

Source .3.17e+06 c&a Water 0.036 Transition Air 0.00122 Shieldt2 1.-7 cm Iron 7.86 Air Gap Air 0.00122 Wall Clad 3.401 cm Iron 7.86 Source Input: Grou.ingMethod - Actual Photon Eneries Nuclide Ci Bq guCiic.m I Bqkinl Ba-I37m

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

M Btar/Date Reviewer/Date Calculation No. Revision M.Berg 5/29/2007 J.Metcalf 5/29/2007 H21C-103 0 C~s-134 ______________

Cs-136 _______________

Cs-I 3.7_______________ __

1-132 ______________ __

1-133 _______________ __

1-134 ______________ __

1- 13,5 _ _ _ _ _ _ _ ________________ _ _ _ _ _ _

Kr-83m_________________ ______ __

Kr-&o_________________

N-1 6 1.1414e-I 001 4.2231le-i 011 3.6000e+i-000 L3320e-005 Rb-S 6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Xe- 13 Im _________________________

Xe-133 ________ ________________

Xe-133in _______ _______________

Xe- 135 ________ ________________

-Xe-135M ________ _______________

Xe-i 37 ________ ________________

Xe-13S _______ ________________ _______

B*uildup: The. materialI reference is Shield 2 Inte2ration Parameters Results - Dose Point E1 -(370.84,916.94,190.66) cm Fluence IFluence 2Rate Exposure Exposure Ener'g AsvtRz MeVlcmin ýsec Ratze Rate fMeN) Photons/sec) 1eV~cm-V1sec with mp"iir1 mRihr No Buildup. Buildup INo Bifl~dup With

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Originator/Date Reviewer/Date Calculation No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21 C-1 03 0 Ref.I Buildup 1.7548 5.490e&OS 2.23ie-01 6.117e+401 3.590e-02 9.845e-02 2.7412 3..210e 09 3.007e-02 6.73&e-02 4.199e-0I 9.410e-01 6.1292 2.9l4e14 S.734e+04 1..469e+O5 942Se-*01 1.586ei-02 6.3 342 6.787e+08 2.115e-02 3.525e+02 2.262e 01 3.770e-01 7.1151 2.1I2e-10 7.519e-03 1.211 e ,04 7.791e400 L.255e- 01 Totals 3.169e11 9,540e-04 1,028e+02 L6Ote-:5 L.726e-02 Results - Dose Point # 2 - (325J2.916.94.190.66) cmI rFuene Fluenef Rate Exposure ERoare Energy ACTiviW- Rate MeVRcm/ RaIete (Niv) (Photomsisec) 7cms1eMeI Wihi minRhir nir No Buildup Buildup: No Buildup Buildup 1.754S  ;.490e-08 2.477e-01 6..828e+o1 3.986e-02 1.09Qe-o1 2.7412 3.210e-09 3.34ge-:02 7.540e+02 4.676e-01 1.053&00 6-1292 2.9i4e11 9.73 Se-04 1.64 7e+05 1.053e+02 1.778e-02 6.3342 6.787e+09 2.363e+02 3.952e+02 2.527e-o1 4.227e-01 7.1151 2.Ii2e+10 8.399e+03 1.357e-04 8.703e-00 1.406e+01 Totals 3.169e+11 1 0-65e+05 1.795e405 1.148e+02 1.935e+02 Re*ults - Dose Point* I 3 - (190.66,916.94.30.48) cm Fluence Fluence Rat Emposure Exposure Rate Energ, Activity Rate MeV/cmw/-er Rate Rate (MeV) MeVlcm.

ehotonis/ec.

'sec IVth mRlhW No Buildup Buildup No Buildup Buildup 1.7548 5.490e-03 6.1 13eO+I I..633e+02 9.837e-0 2.628e-01 2.7412 3.211Oe-09 8.12eQ02 1.787e+03 t.,134e+00 21495e-00 6.1292 2.9-4e-11 2.330e'05 3..885eý5 2. 5,-15eý*02- 4.193e+002 6.33421 6..787e+08 5.642e 2 9.321)e+:02 6.034e-01 9.969e-01 7.1151 2.te-10 2.-04e-04 3.201e-04 2.077e-01 3.317e-01 Totals 3.169e+11 2.545e+-05 4.234e-0-5 2741+02 4.563e+02 Reults - Dose Poin t 4- 2916.94.190.66) cm tluence Fluce e Rate Exposure Exposuire

.Enr*y . Acrvi- Rate "ieVicm"

!le- Rate Rate (MeVj (PhotonsIsec 'E IIeV;cm./s

_________L_1 Meicre C________it!1 inR/hr rnRJir

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Orgntor/Date Reviewer/Date Calculation No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0 Ref.I

'No Builchip Bulildup No Buildup 'With

___ ___ __ _______ ________ Buildup 1.7548 5..490e,+ 08 2.3921e+01 8-042e-01 3.M3e-O2 1.294e-01 2."412 3..21 Oe+OP 3.630e-02 9_598e-O2 5.069e-0 1 1-34 erL-0 6.1292 1.91 4e-, 11 1.173ev-0:5 1-.204e-05 1.267e+02 2_379e+02 6.3342 6_787e+08 2.847er4102 5.2 96e ý-02 3.1145e,-1 5.653e-O1 7.1151 '1112C+10 L0 16e~-'-4 1LS12e.404 I.053e+O1 L87Se--O1 Totals 3.169e+11 1.282e:-0-5 1~OeO

.380e-I0-0 2.5 8-1e~-02

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page C9 (Next 010_)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

riginator/Date Reviewer/Date Calculation No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0 Ref.

Microshield 7.02 Output Main Steam Line Calculation Using CRDA Source MIr SIhield 7.02 Polestar .Applied Tec~hneolog (O6-MSD.L0-7Jd1110)

I I Dare B1 Checked fileneam Run Date Run Time Duraflon NMP U2 Main Steam noimal CRDA-ts7 May 24. 20107 15:57:49 PM 00:00:09 Project Info Case Title Nine Mile Point U2 Descrition Main Steam Line with CRDA Source Geometrv 7 - Cy imder Volume - Side Shields Source Dimensions Heitht 975,36 cm (17 ft)

Radus32 ý167 cm (1 ft 0.7 in' Dose Points 190.6Ocm(6f, cmi(1f2 fl 413 70. 2.4 O.in) 1.0 in)(30ft 916.94cm 3:1 in) y:

.25,12 cm(10.ft. 916,94cm(30ft 190.66cm(6ft 8-0 in) 1.0 in) 3.1 in) 13 90-66 cm (,5 ft 3-1 916ý94 cm (30 ft 04 m( t

_ irL)1.0 min~

• 476-2 cmd 2 .ft 6.0 9 16-94 cm (30 ft 190.66 cm:(6 ft I X m4il) 1.0 inl 3 in),

Shields Shield Dimension MNaterial Density Source 3. 17e+06 an' Water 0.011 Tr_ _ _ _tio Air 0.00122 Shield 2 1.27 cm Iron 7.86 Air Gap Air 0-00122 Wall Clad 3.401 cm Iro 7.86 Source Input: Groupinz Method - Standard In,dices Number of Gr ops: 25 Lower Energy Cutoff: 0,015 Photus : 0i,0: Included

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -C10 (Next Cl )

Project-Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculaton No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0 Ref.I Library: Grove Nuclide Ci Bq Ci/cm- Bqlcm Ba-137m Cs-134 1.0500e+005 3.8850e-+015 3.31iSe-004 1-2254e+ 009 Cs-136 3.2900e+004 12173e+0i 5 I.0377e-004 33M95ee009 Cs-137 6.2SOOe+004 L23236e+015 1.9S08e-004 7.3289e-008 1-131 3.3300e+005 1.2321 le+0!6 1.0503e-005 3-S862e-009 1-132 4.S200e+005 1.7834e+016 1.5203e+005 5-6250e-009 1-133 6.7800e+/-005 2.5086e+016 2.1385e-005 7-9124e-,009 1-134 7.4200e+005 2..7454e+0i6 2.3403e+005 8.6593e+009 1-135 6.3500e-005 2-3495e-0i6 2.0029e+005 7A106e+009 Kr-83m 4.1700e-+004 1.5429e+015 1.3153e+004 44.865e0300 Kr-85 5.0I0Oe-+003 1.8537e-014 15802e-+003 5.S468e+007 Kr-85m 8.7000e+004 3.2190e+015 2.744ie-004 1,0153e+009 Kr-87 1.6600e-005 6-1420e+01 5 5.23 58i004 1L9373e-009 Kr-S8 2.3300e-005 8-62.10e-01-5 7.3491e-+-004 2 71919 e- 09 Kr-89 2.8300e+-005 -0471e+016 SS261e+004 3.3027e-009 N-16 Rb-86 1.0500e+003 3.8950e+'7013 3.3 tIne-i-G02 1.2154e+007 Xe-131m 3.800e-r003 .435-6e+0-i14 1.2238e-003 4,5280e+007 Xe-1333 6.7200e+005 2.4864e+016 2..1196e+005 7 .8424e+-009 Xe.-i33i 2.0S00e+004 7.6960e+014 6.5605e+003 2.4274e-009 Xe-135 2.4400e+005 9.0280e+/-01 5 7.6960e-004 2.1475e+009 Xe-1.3n5m 1.3900e-005 5.1430e+015, 4..3842e-004 1,6222e-+009 Xe-137 6.1200e-005 2.2 644ee+ 0!6 1..9303e-005 7.1422e-i-009 Xe-138 5.7400eý,005 2. 123 8e+0 16 L.8 105.e+005 6.6987e+009 Buildup: The mateiial reference is Shield 2 Integ-ration Parameters

-adiD P 20 Circum~ferential 20*

Y Direction (axial) 50 Results - Dos~e P*ointt # 1 - (3-70.84.91 ý9 4,ý19N.66) cm

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21 C-1 03 0

Fef.I 0.08 9.524e-1E5 1.585e-02 3. 59 6c-02' 2'50ge-05, 5.690e-05 0.1 2.198e-13 1.910e-01 5.,604e-01 19'2 OYe-04 &.574e-04 0-15 5.0ieI .00e~O 2.199~e,05 8."34t+O 3.620e-ý02 0.2w 1.504e-46 1.204e7+0O6 6.784e-,06 2.ý1214e+03 l1,97e.-04 0.3 1.069e-46 5.137e+06 3-238e+-07 9.745t,-03 6.143e-04 0.4 2.591e416 3.149e+0g7 1.924e+0S 6-135e--04 3.748e405

0. 4.426e- 16 1.017eýOS 5 -721e+0 8 1.997e÷OS 1 VL-3e406 0.6 1 4.143e--16 I.5.52e-GS 7M98e+08 3.029e-05 Lf.558e+06

0. 7.791e4-16 6.079e-.O0 .1.644e+09 1.156e+/-ý06 S.2e6 1.0 3.180e-+16 4-')76e--0S I ,6 I8e+09 7.883e-'--05 2.PSMe+06 1.3 2.528e=146 8.5S4e+/-08 1.532t,109 1.444e--06 4.'-59e-:-06 2.0 1 139e-16 1304e-09 3-336e+09 2.016e+/--06 _5

.15 9e-06 4

3.0 1-868e-4-15 2.344e 08 5, 044eL+D8 3.lS0e+/ 6.843e+-0;3 4.0 4-689e- 14 P.162eýfl7 1.770e-08 1. 133e-05 2.189e.+05 Toas 3.3"',+/-1f JL'e" 09 1.24lee÷I0 6,412 e-i06 2.146e-,07

_______ Results -Dose Point # 3 - CM _____

Fhtence Fluence Rate Exosr Ex~posure Energy Activit-v Rate MVcJe RareR/

(AMfN) (Phototisisec) MeA71iclnse-c with mR/hi- IY t No Buildup Buildup INo Buildup Buildup 0.01-5 4 7 42e-,I 0.000e-,-00 4.!4-,9e- 19 0.000e-00 3.799e-20 0.3 i.610e+16 3,873e-l121 3.147e:-1.8 3.838e-l'2-3 3.2l18e-20 0.04 4-601e4-,13 5iSS6e-52 L 4 1A9e---2 0 1.590e-54 6.274e-23 0-06 1.517e-r14 2.993e-13 4.984-c-13 5.923-t-16 9.899e-16 O.0 9.524e4-15 &.709e-02 I.958e-01 1.378e-04 3.99e-04 0.1 21.198e--13 7,784e-01 i2-254e+0 0 1 .l9 1e -03 3.449e-03 015 -5.f, 11e-4I5 L598te05 6.S44e+05 2. 63 2 e:02 11 L7c-03 0.2 1.504e-,16 3..57le-z06 1-940e-07 6.302e-03 3.424e-04 0.3 .1M06%÷16 1.439e-07 S.664e+0)7 2.729te-r-04 1.643e+05 0.4 21.5,1erý16 &.575e-07 988e+08 1,671t+-05 9.719e-05

0. 5 4.426e4+16 2-720e-08 1-456e+99 5.3 3 &-+05 2.858e+~06 0.6 4.143e+16 4-..OMe+/--s 12005e-09 7.986e-+05 3.913e+06

I31 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -C12.

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Onginator/Date Reviewer/Date CaIculaton No Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0

[Ref.I 0-08 9.524e-I 5 1..585e-02 3.596e-02 2.508e-05 5.690e&O5 0.1 2.t98e&13 [L910e-01 5.604e-0I 2.922e-04 S.574e-04 0-15 5.5 le+15 5.000e-04 2.198e-05 8.2 3 4e+01 3<620e-02 0.2 1.504e-16 1.204e--06 6.784e-;-06 2.124e+03 1.197e+04 0.3 i.069e-16 5.137e,-06 3.238e-07 9.745e+03 6.143e-04 0.4 2.59!e-16 3.149e-07 1.924e-08 6.135e-04 33748e+05 0.5 4.426eý16 1.017e+08 5.721e+06 1.997e-t05 1.123e,06 0,6 4.143e-16 1.552e-09 7980e-O8 3.029e-4-05 L-55Se+06 0.8 7.791e+16 6.079e+-08 2..644e-09 1.156e+06 5.028e06 1.0 3.I80e+16 4.276e÷-08 1.618e=09 7.883e+05 2-982e+-,06 1.5 2.528 e+16 S.584+e-08 2.532eý09 1.444e+06 4.259-06 2.0 2.139e,16 1.304eý09 3.336e;09 2.016e+06 5.159e-06 3.0 1.868e+ 15 2.344e+- 03 5.044e-08 3.180e+05 6.843e+05 4.0 4.689e+ 14 9.162e-07 1.770e-OS 1.133e+05 21189+e05 7

Totals 3.322 e17 3.818e.09 1.241e+10 6.412e.+06 2.146e÷01 Results - Dose Point # 3 - (190.66,916.94.30.48) cm fluence Fhlence Rate Exposaure Exposure Energy AcTivity Rate IfeVcm111sec Raae (MeV) (Pho to. is.ec MeVlcm*,sec With mR1,hr No Buildup BoBildup Buildup Bi dup 0.015 4.7421e15 0.000e,00 4.429e-19 0.000e+00 3.799e-20 0.03 i.610e-16 3.873e-121 3.247e-18 3.-3Se-I23 3.218e-20 0.04 4,60e-t13 5.856e-52 1.419e-20 2.590e-54 6.274e-2 0.06 i.517e-I4 2.983e-13 4.984e-13 5.925e-16 9.899e-16 0.08 9.524eý-15 8,708e-02 1.958e-0t 1.378e-04 3.099e-04 0.1 2.t98eýe3 7784e-01 2.254e-00 1.19le-03 3.449e-03 0U5 5.511 e15 L59Se+05 U.44e-05 2.632e+02 1.127e-03 0.2 1.504e,- 16 3.57ie-06 1.940e+07 6.302e-03 3.424e 04 0.3 1.069e+16 1.439e+07 8.664e-07 2.729e+04 1.643e+05 0.4 2.5 9 e*i16 8.575e+07 4.988e+08 i.671e-05 9.719e-05 0.5 4.426e-16 .720e-+0S 1456e+09 5.338e+05 2.858e-06 0.6 4.A43e+16 4.091e--08 2005e:09 7,986e+05 3913e06

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Oiiginator/Date TRevewedDate Calculaon No. Revision M.Berg 5/29/2007 J. Metcalf 5/29/2007 H21C-103 0 Ref.I.

0.3 7.791e+16 L..570e-009 6.52Se409 2.987e+06 1..242 ,e-,07 7

1.0 3-180e*-16 L.8Oe+09 3.95 te-+09 2.006e+ý06 .282e-+06 1.5 2.52Se-16 2,.133e-09 6.08le+09 3.g89e+--06 1023e-07 2.0 2.139e,16 3.197e-09 7.948e+09 4.944e+06 I.229e-+07 3.0 1.868eý-15 5A668e08 11:94e+/-09 7.690e+: 05 61t9e+06 4.0 4.689e+14 2.201e+.0 4.175e-08 2.723e+05 5.165e+05 Totals 3.322e-.17 9,561e+09 M3,19e+I0 1.610e+07 5.230e÷07 Results - Dose Point # 4 - (76.2.916.94,190.66) cm Fluence. Fluence Rate Exposure Exposure Activity Rate ,MeVicmrnsec Rate Ra Energy (MeV) (Photousisec.) Mevicmnfsec With mR/hit No Buildup Buildup No Buildup I_ Buildup 0.015 4.742e÷ 5 O.00e-*00 4.089e-19 0.000e+00 3.507e-20 0.03 1.610e-16 1.945e-173 2.997e-18 1.928e-175 2.970e-20 0104 4..60!e+13 5.204e-75 1.309e-20 2.301e-77 5.791e-23 0.06 1.517e+ 14 6.764e-21 9.421e-20 1.343e-2. 1,87e-22 0U0S 9.524e-i5 1.315e-05 3.21 1e-05 2.082e-08 5.08le-0R 0.1 2.19e-'13 2.847e-03 9..'250e-03 4,356e-06 1.415e-05 0.15 5.511e15 6.880e-03 3.619e+04 1.133e+01 5.960e-01 0.2 1.504e-16 3.092e--05 2.222e-'-06 5.458e-02 3.922e-03 0.3 1.069e-,16 2.066e-06 1.739e+07 3.920e403 3..2 9e÷04 0.4 2.59te-16 1.551e-07 1-283e+08 3.023e-04 2.500e-05 0.5 4.426e+16 5.706e+07 4.333e +0S 1,120e+-05 8.516e+05 0.6 4.i43e. 16 9.573e+07 6.595e-ý08 1.69e*,05 1.287&-06 0.8 7.791e16 4.304e+-08 2.458e+09 S. M6e+05 4.676e-706 1.0 3.i80e-16 3.341e+08 1.627e-09 6. 159e--0 -5 2.998e+06 1.5 2.528e+16 7.S6ie-+08 2.873e-09 1.323e-, 06 4.835e-06 2.0 2. 139e-16 1.306e-09 4.040e+09 1020e+06 6.247e+06 3.0 1.S68e+15 2.584e+08 6.493e+08 3.505e+05 9.909e+05 4.0 4.689e+14. 1.058e,-08 2.344e+-08 1.309,--,05 2.899e,-05 Totals 3322e+17 3.392e:09 1312e+10 5.592e+06 1,235e+0-

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Calculation No. Revision

[OignaorDaeR~eviewer/Date J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

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

" Review Regulatory Guide 1.183 (Reference 1 of the main body of the calculation) to ensure that methods being applied to the NMP LOCA analysis conform to the requirements of that document.

" Using the input data compiled in Reference 7 of the main body of the calculation, prepare a RADTRAD (Reference 2 of the main body of the calculation) analysis of the NMP LOCA radiation doses for offsite (EAB 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 for Case 2 (Appendix E).

Model:

The activity release can be simplified to the model shown in Figure D-1 below.

Figure D-1: CRDA Case 2 Model I ,Soure*Main Condenser (MC)

Environment Control Room (CR)

Volumes:

Source: 7.17E+06 (calculated in main body)

Main Condenser (MC): 9.7E+04 (see Design Input of main body)

Control Room (CR): 2.02E+05 (see Design Input of main body)

Junctions:

1. Pathway Description 1 Source -- MC 1.468E+04 cfm for 24 hrs (calculated in main body) 2 MC -- Environment 5.OOE+03 cfm for 24 hrs (see Design Input of main body) 3 Environment-- CR IE+06, or infinite flowrate into the control room is credited per Assumption 3 in the main body of this calculation.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D2-(Next 0-)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. T Revision J. Metcalf 5/29/2007 Appendix E H21 C-1 03 0 4 1CR' Environment I 1E+06, or infinite flowrate out of the control room is credited per Assumption 3 in the main body of this calculation 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-1 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 (.psi)

Each RADTRAD 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, X/Qs etc.

Nuclide Information File (nij)

The 63 isotopes used in RADTRAD are listed in the nmp2.nif file. One will find the radionuclide inventories listed as Ci/MWt in this file.

Release FractionFile (rfi):

The file nmp2-crda.rft was used. This file contains information specific to the AST source term, i.e., the fraction and timing of each release phases.

Dose Conversion FactorsFile (inp)

The Dose Conversion Factors file used for this RADTRAD run is based on the Federal Guide Reports 11 and 12. The file used is nmp2.inp. This file is a modification of the default RADTRAD file called FGR 11 & 12.INP to include additional radionuclides.

Results (Unit 2 CR):

Case 2 RADTRAD EAB 1.03 LPZ 1.17 Control Room 2.31 Results (Unit 2 CR for Release from Unit I and Unit 1 CR for Release from Unit 2):

The Unit 1 CR dose due to the Unit 1 CRDA Case 2 (from Reference 4 of the main body of the

41 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D3 (Next D4_)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __Rs JOriginator/Date Reviewer/Date .aclbnN.Rvso J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

calculation) is 1.61 rem TEDE. The Unit 2 CR dose due to the Unit 2 CRDA Case 2 (calculated above) is 2.31 rem TEDE. A comparison of the relevant X/Qs (stack releases) is as follows (from/to):

0-2 hours 2-8 hours 8-24 hours U1/U1 2.27E-04 sec/m 3 1.26E-04 sec/m 3 4.30E-05 sec/m 3 UI/U2 1.10E-04 sec/m 3 6.16E-05 sec/m 3 2.31 E-05 sec/m 3 U2/U2 8.03E-05 sec/m 3 4.48E-05 sec/m 3 1.68E-05 sec/m 3 U2/U1 4.18E-05 sec/m 3 2.30E-05 sec/m 3 8.94E-06 sec/m 3 This comparison shows that since:

1. No credit is taken for emergency filtration in the dose analysis of either control room (and since the finite volume gamma dose correction for Unit 1 is only slightly more favorable than for Unit

2) and

2. Acceptable CR doses have been obtained for both Ul/U1 and U2/U2, then the U1/U2 CR dose and the U2/U1 CR dose must both be acceptable. In fact, U1/U2 < U1/U1 -

1.61 rem TEDE and U2/UI < U2/U2 = 2.13 rem TEDE.

,2_

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Project-Nine Mile PointNuclear Station Unit: 2 Disposition: __

I Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Appendix D-1: Primary Input (.psi) file, Plant Scenario File, nmp2crda-2pmp'.psf Radtrad 3.03 4/15/2001 NMP2-CRDA-2pump-final Nuclide Inventory File:

C:\RADTRAD303\defaults\nmp2.nif Plant Power Level:

7.3210E+03 Compartments:

4 Compartment 1:

Source 3

.7.1700E+06 0

0 0

0 0

Compartment 2:

MC 3

9.7000E+04 0

0 0

0 0

Compartment 3:

CR 1

2.0200E+05 0

0 0

0 0

Compartment 4:

Environment 2

0.OOOOE+00 0

0 0

0 0

Pathways:

4

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Project, Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Pathway 1:

Source to MC 2

1 Pathway 2:

MC to Environment 2

4 1

Pathway 3:

Environment 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 1.OOOOE+00 c:\RADTRAD303\defaults\nmp2.inp c:\RADTRAD303\defaults\nmp2-crda.rft O.OOOE+00 O.OOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:

0 0.OOOOE+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0

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Project.-Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 R -ef-.-- I 0

0 0

0 0

0 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0 0

0 0

0 0

0 Pathways:

4 Pathway 1:

0 0

1 3

0.0000E+00 1.0000E+02 1.4680E+04 2.4000E+01 1.OOOOE+00 0.OOOOE+00 7.2000E+02 1.OOOOE+00 0.OOOOE+00 1

3

4-1ý ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D7 Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

OriginatorfDate Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

O.OOOE+00 1.OOOOE+01 1.4680E+04 2.4000E+01 1.0000E+00 O.OOOOE+00 7.2000E+02 1.OOOOE+00 O.OOOOE+00 1

3 0.OOOOE+00 1.OOOOE+01 1.4680E+04 2.4000E+01 1.OOOOE+00 O.OOOE+00 7.2000E+02 1.0000E+00 0.0000E+00 0

0 0

0 0

0 0

Pathway 2:

0 0

1 3

0.OOOE+00 1.0000E+02 5.0000E+03 2.4000E+01 1.0000E+00 0.0000E+00 7.2000E+02 1.0000E+00 0.OOOOE+00 1

3 0.0000E+00 1.0000E+01 5.0000E+03 2,4000E+01 1.0000E+00 0.OOOOE+00 7.2000E+02 1.0000E+00 0.0000E+00 1

3 0.000OE+00 1.0000E+01 5.OOOOE+03 2.4000E+01 1.0000E+00 0.0000E+00 7.2000E+02 1.0000E+00 0.0000E+00 0

0 0

0 0

0 0

Pathway 3:

0 0

0 0

0 1

2

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __Ri OnginatoriDate Reviewer/Date Calculaion No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

O.OOOQE+00 1.OOOOE+06 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

2 0.OOOOE+00 1.0000E+06 0.OOOOE+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

EAB 4

1 3

0.0000E+00 2.9600E-05 8.OOOOE+00 0.OOOOE+00 7.2000E+02 0.0000E+00 1

3 0.OOOOE+00 3.5000E-04 8.OOOOE+00 0.0000E+00 7.2000E+02 0.OOOOE+00 0

Location 2:

LPZ 4

1 7

0.0000E+00 1.4200E-05 3.0000E-01 1.4200E-05 2.3000E+00 1.4200E-05

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D9 (Next DI1 J)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

8.OOO0E+00 5.4100E-07 2.4000E+01 2.3100E-07 9.6000E+01 7.6500E-08 7,2000E+02 OO0OOE+00 1

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

Location 3:

CR 3

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.OOOOE+00 1

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

7 0.OOOOE+00 4.4800E-05 3.OOOOE-01 8.0300E-05, 2.3000E+00 4.4800E-05 8.0000E+00 1.6800E-05 2.4000E+01 1.2000E-05 9.6000E+01 8,8300E-06 7.2000E+02 0.OOOOE+00 Simulation Parameters:

0 Output Filename:

c:\RADTRAD303\NMP2CRDA-2pmp"'.out 1

1 1

0 0

End of Scenario File

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D10 (Next Dl 1)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Appendix D-2: Secondary Input (.nif, .rft, .inp) files Appendix D-2.1: Nuclide Information File, nmp2.nif Nuclide Inventory Name:

ST general Power Level:

0.1000E+01 Nuclides:

63 Nuclide 001:

Kr-83m 1

0.6696E+04 0.8300E+02 3.270E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

Kr-85m 1

0.1612800000E+05 0.8500E+02 6.82E+03 Kr-85 0.2100E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 003:

Kr-85 1

0.338613048E+09 0.8500E+02 3.93E+02 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-87 1

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

Kr-88 1

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D1 1 (Next D12 -)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

0,1022400000E+05 0.8800E+02 1.83E+04 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nucide 006:

Rb-86 3

0.1612224000E+07 0.8600E+02 0.729E+02 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 007:

Rb-88 3

0.1062000000E+04 0.8800E+02 1.000E-06 none O.0OOOE+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 0.0000E+00 none 0.0000E+00 Nuclide 009:

Sr-90 5

0,9189573120E+09 0.9000E+02 3.14E+03 Y-90 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 3.10E+04

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D12 (Next D13_

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculafon No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 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 9

0.2304000000E+06 0.9000E+02 3.24E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 3.18E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuciide 014:

Y-92 9

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

Y-93 9

0.3636000000E+05 0,9300E+02 3196E+04 Zr-93 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00

51 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D13, (Next D14_)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Nuclide 016:

Zr-95 9

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 9

0.6084000000E+05 0.9700E+02 4.51 E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 4.48E+04 none 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 019:

Mo-99 7

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 7

0.2167200000E+05 0.9900E+02 4.49E+04 Tc-99 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 021:.

Ru-103 7

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D- 14 (Next 0D15-)

Project.-Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0

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-105 7

0.1598400000E+05 0.1050E+03 3.01 E+04 Rh-105 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.76E+04 Rh-106 0.1000E+01 none O.OOOOE+00 none 0.0000E+00 Nuclide 024:

Rh-105 7

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

Sb-127 4

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

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D1 5 (Next -D16 -)

Project: Nine Mile Point Nuclear Station Unit: -2_ Disposition: __Rs Originator/Date Reviewer/Date Calculation No.

J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.0000E+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 3.00E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 4.05E+02 Te-127 0.9800E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 8.76E+03 1-129 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

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

Te-131m 4

0.1080000000E+06 0.1310E+03 3.97E+03 Te-131 0.2200E+00 1-131 0.7800E+00 none 0.OOOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D1 6 (Next 0D17-)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Nucide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 3.85E+04 1-132 0.1000E+01 none O.0000E+00 none 0.0000E+00 Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03 2.71 E+04 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+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 Nuclide 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 Nuclide 036:

1-134 2

0.3156000000E+04 0.1340E+03 6.03E+04 none 0.0000E+00 none O.0000E+00 none 0.0000E+00 Nuclide 037:

1-135 2

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D17 (Next _D188)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

OrginatorlDate Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

0.2379600000E+05 0.1350E+03 5.16E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0,0000E+00 Nudide 038:

Xe-133 1

0.453 1680000E+06 0.1330E+03 5.27E+04 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 039:

Xe-133m 1

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

Xe-1 35 1

0.3272400000E+05 0.1350E+03 1.91 E+04 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nucide 041:

Xe-135m 1

0.91800000E+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 0.1380E+03 4.50E+04

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D18 (Next D19-)

Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculaton No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 043:

Cs-1 34 3

0.6507177120E+08 0.1340E+03 7.29E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 044:

Cs-136 3

0.1131840000E+07 0.1360E+03 2.28E+03 none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 045:

Cs-1 37 3

0.9467280000E+09 0.1370E+03 4.35E+03 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 046:

Ba-139 6

0.4962000000E+04 0.1390E+03 4.89E+04 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 047:

Ba-140 6

0.1100736000E+07 0.1400E+03 4.71E+04 La-140 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00.

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page _D1 9 (Next D20_)

Project. Nine Mile Point NuclearStation Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Nuclide 048:

La-140 9.

0.1449792000E+06 0.1400E+03 5.12E+04 none O.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 049:

La-141 9

0.1414800000E+05 0.1410E+03 4.45E+04 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 050:

La-142 9

0.5550000000E+04 0.1420E+03 4.29E+04 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 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

0.1 188000000E+06 0.1430E+03 4.11E+04 Pr-143 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 053:

Ce-144 8

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D2D20 (Next 0D21 Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J.Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

0.2456352000E+08 0.1440E+03 3.70E+04 Pr-144m 0,1800E-01 Pr-144 0.9800E+00 none 0.0000E+00 Nuclide 054:

Pr-143 9

0,1171584000E+07 0.1430E+03 3.97E+04 none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+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 0.0000E+00 Nuclide 056:

Np-239 8

0.2034720000E+06 0.2390E+03 5.78E+05 Pu-239 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 057:

Pu-238 8

0.2768863824E+10 0.2380E+03 1.45E+02 U-234 0.1000E+01 none 0.OOOE+00 none 0.0000E+00 Nuclide 058:

Pu-239 8

0.7594336440E+12 0.2390E+03 1.34E+01

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D21 (Next D22 -)

Project. Nine Mile Point Nuclear Station Unit: 2 Disposition: Rs Originator/Date Reviewer/Date Calcuia~on No Revision J. Metcalf 5/29/2007 Appendix E H21C-l03 0 Ref.

U-235 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nucide 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 0.241E+03 5.49E+03 Am-241 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 061:

Am-241 9

0.13664441E+11 0.241E+03 7.48E+00

• Np-237 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 062:

Cm-242 9

0.14083200E+08 0.242E+03 1.85E+03 Pu-238 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 063:

Cm-244 9

0.56488104E+09 0.244E+03 1.23E+02 Pu-240 0.1000E+01 none 0.0000E+00 none 0.0000E+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D22 (Next D23_)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 End of Nuclear Inventory File

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D23 (etD24 -

Project:Nine Mile Point Nuclear Station Unit: 2 Disposition:

Orinator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21 C-1 03 0 Ref.

Appendix D-2.2: Release Fraction File, nmp2-crda.rft Release Fraction and Timing Name:

NMP2 - CRDA with fuel melting Duration (h): Control Rod Drop Accident 0.0010D+00 O.OOOOD+00 O.OOOOD+00 O.OOOOD+00 Noble Gases:

1.7560E-03 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Iodine:

1.6930E-03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cesium:

1.9870E-03 O.OOOOE+00 O.OOOE+00 O.OOOE+00 Tellurium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 Strontium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Q.OOOOE+00 Barium:

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

0.OOOOE+00 O.OOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:

O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOE+00 Non-Radioactive Aerosols (kg):

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 End of Release File

4 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D24 (Next _D25 -

Project: Nine Mile Point NuclearStation Unit: 2 Disposition: __

[Oiginator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Appendix D-2.3: Dose Conversion Factor File, nmp2.inp FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 Implicit daughter halflives (m)less than 90 and less 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 Including:Y-91m Sr-92 Y Y-90 Y Y-91 Y Y-92 Y Y-93 Y Zr-95 D Zr-97 Y Including:Nb-97m, lncluding:Nb-97 Nb-95 Y Mo-99 Y Tc-99m D Ru-103 Y Including:Rh-103m Ru-105 Y Ru-106 Y Including:Rh-106 Rh-105 Y Sb-127 W Sb-129 W Te-127 W Te-127m W Te-129 W Te-129m W Including:Te-129 Te-131m W Including:Te-131 Te-132 W 1-131 D

C-3 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D25 (Next D26 Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J,Metcalf 5/2912007 Appendix E H21C-103 0 Ref.

1-132 D 1-133 D 1-134 D 1-135 D Including:Xe-135m Xe-1 33 Xe-133m Xe-135 Xe-135m Xe-1 38 Cs-134 D Cs-136 D Cs-137 D Including:Ba-137m Ba-139 D Ba-140 D La-140 W La-141 D La-142 D Ce-141 Y Ce-143 Y Ce-144 Y Including:Pr-144m, Including:Pr-144 Pr-143 Y Nd-147 Y Np-239 W Pu-238 Y Pu-239 Y Pu-240 Pu-241 Am-241 Cm-242 Cm-244 CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC Kr-83m GONADS 1.710E-18 5.572E-15 5.855E-15 6.160E-19-1.OOOE+00 0.OO0E+00 0.OOOE+00 BREAST 5.050E-18 9.498E-15 9.980E-15 1.050E-18-1.OOOE+00 O.OOOE+00 O.OOOE+00 LUNGS 1.640E-19 1.266E-16 1.331E-16 1.400E-20-1.OOOE+000O.OOOE+00 O.OOOE+00 RED MARR 3.830E-19 5.617E-16 5.902E-16 6.210E-20-1.OOE+00 0.OOOE+00 0.000E+00 BONE SUR 2.250E-18 3.437E-15 3.612E-15 3.800E-19-1.OOOE+OO O.OOOE+00 0.OOOE+00 THYROID 6.430E-19 7.698E-16 8.088E-16 8.510E-20-1.OOOE+00 0.OOOE+00 0.OOOE+00 REMAINDER 5.300E-19 1.393E-15 1.464E-15 1.540E-19-1.OOE+00 O.OOOE+00 O,0OOE+00 EFFECTIVE 1.500E-18 3.437E-15 3.612E-15 3.800E-19-1.OOOE+00 O.OOOE+00 O.OOOE+00 SKIN(FGR) 3.560E-17 1.167E-13 1.226E-13 1.290E-17-1.OOOE+00 O.OOOE+00 O.OOOE+00 Kr-85m GONADS 7.310E-15 2.594E-12 3.653E-12 1.570E-16-1.OOOE+00 0O0OOE+00 0.OOOE+00 BREAST 8.410E-15 2.527E-12 3.560E-12 1.530E-16-1.000E+00 O.OOOE+00 O.OOOE+00 LUNGS 7.040E-15 2.379E-12 3.351E-12 1.440E-16-1.OOOE+00 O.OOOE+00 O.OOOE+00 RED MARR 6.430E-15 2.346E-12 3.304E-12 1.420E-16-1.OOOE+00 0.OOOE+00 0.000E+00 BONE SUR 1.880E-14 5.286E-12 7.446E-12 3.200E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D26 (Next D27_)

Project.-Nine Mile Point NuclearStation Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

THYROID 7.330E-15 2.395E-12 3,374E-12 1.450E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 REMAINDER 6.640E-15 2.313E-12 3.257E-12 1.400E-16-1.OOOE+00 0.000E+00 O.OOOE+00 EFFECTIVE 7.480E-15 2.511E-12 3.537E-12 1.520E-16-1.OOOE+00 O.OOE+00 O.OOOE+00 SKIN(FGR) 2.240E-14 2.247E-1 13.164E-1 11.360E-1 5-1.0O0E+00 O.OOOE+00 O.OOOE+00 Kr-85 GONADS 1.170E-16 8.121E-14 1.704E-12 2.820E-18-1.OOOE+00 O.OOOE+00 O.OOOE+00 BREAST 1.340E-16 7.891E-14 1.656E-12 2.740E-18-1.OOOE+00 O.OOOE+00 O.OOOE+00 LUNGS 1.140E-16 7.056E-14 1.481E-12 2.450E-18-1.OOE+00 O.OOOE+00 O.OOOE+00 RED MARR 1.090E-16 6.998E-14 1.469E-12 2.430E-18-1.OOOE+00 O.OOOE+00 0.000E+00 BONE SUR 2.200E-161.287E-13 2.702E-12 4.470E-18-1.OOOE+00 0.OOOE+00 0.000E+00 THYROID 1.180E-16 7.459E-14 1.565E-12 2.590E-18-1.OOOE+00 0.OQOE+00 0.OOOE+00 REMAINDER 1.090E-16 6.941E-14 1.457E-12 2.410E-18-1.OOOE+00 O.OOOE+00 O.OOOE+00 EFFECTIVE 1.190E-16 7.603E-14 1.596E-12 2.640E-18-1.OOOE+00 O.OOOE+00 O.OOOE+00 SKIN(FGR) 1.320E-14 2.304E-11 4.835E-10 8.OOOE-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 Kr-87 GONADS 4.OOOE-14 4.962E-12 5.026E-12 7.610E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 BREAST 4.500E-14 4.740E-12 4.802E-12 7.270E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 LUNGS 4.040E-14 4.603E-12 4.663E-12 7.060E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 RED MARR 4.OOOE-14 4.708E-12 4.769E-12 7.220E-16-1.OOOE+00 0.OOOE+00 0.000E+00 BONE SUR 6.020E-14 6.514E-12 6.598E-12 9.990E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 THYROID 4.130E-14 4.473E-12 4.531 E-12 6.860E-16-1.OOOE+00 0.OOOE+00 0.OOE+00 REMAINDER 3.910E-14 4.590E-12 4.650E-12 7.040E-16-1.OOOE+00 0.OOE+00 0.OOOE+00 EFFECTIVE 4.120E-14 4.773E-12 4.835E-12 7.320E-16-1.OOOE+00 0.OOOE+00 0.000E+00 SKIN(FGR) 1.370E-1 3 8.802E-11 8.916E-1 11.350E-14-1.OOE+00 O.OOOE+00 0.OOOE+00 Kr-88 GONADS 9.900E-14 2.278E-1 1 2.655E-1 11.800E-1 5-1.OOOE+00 0.000E+00 0.OOOE+00 BREAST 1.110E-13 2.177E-11 2.537E-11 1.720E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 LUNGS 1.010E-13 2.139E-11 2.493E-11 1.690E-15-1.OOE+00 0.OOOE+00 0.OOE+00 RED MARR 1.OOOE-13 2.190E-11 2.552E-11 1.730E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 BONE SUR 1.390E-13 2.886E-11 3.363E-11 2.280E-15-1.OOOE+00 0.OOOE+00 0.000E+00 THYROID 1.030E-13 2.012E-11 2.345E-11 1.590E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 REMAINDER 9.790E-14 2.139E-1 1 2.493E-1 11.690E-1 5-1.OOOE+00 0.OOOE+00 0.OOOE+00 EFFECTIVE 1.020E-1 3 2.202E-1 1 2.567E-11 1.740E-1 5-1.000E+00 0.OOOE+00 O.OOOE+00 SKIN(FGR) 1.350E-1 3 5.607E-1 1 6.534E-1 1 4.430E-1 5-1.OOOE+00 0.OOOE+00 0.OOOE+00 Rb-86 GONADS 4.71 OE-1 5 2.788E-12 5.187E-1 1 9.740E-1 7-1.OOOE+00 1.340E-09 2.150E-09 BREAST 5.340E-15 2.662E-12 4.953E-11 9.300E-17-1.OOOE+00 1.330E-09 2.140E-09 LUNGS 4.710E-15 2.553E-12 4.750E-11 8.920E-17-1.OOOE+00 3.300E-09 2.140E-09 RED MARR 4.640E-15 2.619E-12 4.873E-1 1 9.150E-17-1.O0E+00 2.320E-09 3.720E-09 BONE SUR 7.050E-15 3.635E-12 6.764E-11 1.270E-16-1.OOOE+00 4.270E-09 6.860E-09 THYROID 4.840E-1 5 2.599E-1 2 4.836E-1 1 9.080E-1 7-1.OOE+00 1.330E-09 2.140E-09 REMAINDER 4.520E-15 2.542E-12 4.729E-1 1 8.880E-17-1.000E+00 1.380E-09 2.330E-09 EFFECTIVE 4.810E-1 5 2.665E-12 4.958E-1 19.31 OE-17-1.OOOE+00 1.790E-09 2.530E-09 SKIN(FGR) 4.850E-14 2.210E-10 4.111E-09 7.720E-15-1.OOOE+00 0.OOE+00 0.0OOE+00 Rb-88 GONADS 3.260E-14 2.788E-12 5.187E-11 9.740E-17-1.OOOE+00 1.310E-12 2.150E-09 BREAST 3.670E-14 2.662E-12 4.953E-11 9.300E-17-1.OOOE+00 1.430E-12 2.140E-09 LUNGS 3.310E-14 2.553E-12 4.750E-11 8.920E-17-1.00OE+00 1.470E-10 2.140E-09

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/2912007 Appendix E H21C-103 0 Ref.

RED MARR 3.300E-14 2.619E-12 4.873E-11 9.150E-17-1.000E+00 1.450E-12 3.720E-09 BONE SUR 4.620E-14 3.635E-12 6.764E-11 1.270E-16-1.000E+00 1.470E-12 6.860E-09 THYROID 3.370E-14 2.599E-124.836E-11 9.080E-17-1.OOOE+00 1.370E-12 2.140E-09 REMAINDER 3.210E-14 2.542E-12 4.729E-11 8.880E-17-1.000E+00 1.380E-11 2.330E-09 EFFECTIVE 3.360E-14 2.665E-12 4.958E-1 1 9.310E-17-1.OOOE+00 2.260E-1 I 2.530E-09 SKIN(FGR) 1.830E-13 2.210E-10 4.111E-09 7.720E-15-1.OOOE+00 0.0OOE+00 0.OOE+00 Sr-89 GONADS 7.730E-17 7.155E-14 1.436E-12 2.490E-18-1.OOOE+00 7.950E-12 8.050E-12 BREAST 9.080E-17 7.212E-14 1.447E-12 2.510E-18-1.OOOE+00 7.960E-12 7.980E-12 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-18-1.000E+00 1.590E-10 1.610E-10 THYROID 7.600E-17 6.063E-14 1.217E-12 2.110E-18-1.O00E+00 7.960E-12 7.970E-12 REMAINDER 6,710E-17 5.603E-14 1.124E-12 1.950E-18-1.000E+00 3.970E-09 8.250E-09 EFFECTIVE 7.730E-17 6.523E-14 1.309E-12 2.270E-18-1.000E+00 1.760E-09 2.500E-09 SKIN(FGR) 3.690E-14 1.914E-10 3.841E-09 6.660E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 Sr-90 GONADS 7.780E-18 9.590E-15 2.014E-13 3.330E-19-1.OOOE+00 2.690E-10 5.040E-11 BREAST 9.490E-18 1.008E-14 2.116E-13 3.500E-19-1.OOOE+00 2.690E-10 5.040E-11 LUNGS 6.440E-18 6.307E-15 1.324E-13 2.190E-19-1.000E+00 2.860E-06 5.040E-11 RED MARR 5.440E-18 5.558E-15 1.167E-13 1.930E-19-1.000E+00 3.280E-08 6.450E-09 BONE SUR 2.280E-17 2.393E-14 5.025E-13 8.310E-19-1.OOOE+00 7.090E-08 1.390E-08 THYROID 7.330E-18 7.171E-151.506E-13 2.490E-19-1.000E+00 2.690E-10 5.040E-11 REMAINDER 6.11 OE-1 8 6.422E-1 5 1.348E-1 3 2.230E-1 9-1.OOOE+00 5.730E-09 6.700E-09 EFFECTIVE 7.530E-1 8 8.179E-15 1.717E-1 3 2.840E-1 9-1.OOOE+00 6.470E-08 3.230E-09 SKIN(FGR) 9.200E-1 5 4.032E-1 2 8.465E-1 11.400E-1 6-1.000E+00 0.OOOE+00 0.000E+00 Sr-91 GONADS 3.380E-14 2.155E-11 5.062E-11 1.026E-15-1.000E+00 5.650E-11 2.520E-10 BREAST 3.830E-14 2.059E-11 4.838E-11 9.806E-16-1.000E+00 1.740E-11 3.676E-11 LUNGS 3.370E-14 1.970E-11 4.626E-11 9.376E-16-1.OOOE+00 2.130E-09 1.055E-1I RED MARR 3.310E-14 2.011E-11 4.722E-11 9.570E-16-1.OOOE+00 2.230E-11 5.659E-11 BONE SUR 5.200E-14 2.852E-11 6.709E-11 1.360E-15-1.000E+00 1.270E-11 2.070E-11 THYROID 3.470E-14 2.035E-11 4.782E-11 9.693E-16-1.OOOE+00 9.640E-12 1.968E-12 REMAINDER 3.240E-14 1.948E-11 4.573E-1 1 9.268E-16-1.000E+00 5.780E-10 2.557E-09 EFFECTIVE 4.929E-14 2.057E-11 4.832E-11 9.793E-16-1.OOOE+00 2.577E-10 8.455E-10 SKIN(FGR) 8.140E-14 1.748E-10 3.987E-10 8.080E-15-1.000E+00 0.OOOE+00 0.OOOE+00 Sr-92 GONADS 6.610E-14 1.593E-11 1.830E-11 1.300E-15-1.OOOE+00 1.020E-.11 8.180E-11 BREAST 7.480E-14 1.520E-1 11.745E-1 11.240E-1 5-1.OOOE+00 6.490E-1 2 1.700E-1 1 LUNGS 6.670E-14 1.483E-1 1 1.703E-1I 1.210E-15-1.000E+00 1.050E-09 7.220E-12 RED MARR 6.620E-14 1.520E-11 1.745E-11 1.240E-15-1.OOOE+00 6.980E-12 2.290E-11 BONE SUR 9.490E-14 2.010E-11 2.308E-11 1.640E-15-1.OOOE+00 4.360E-12 8.490E-12 THYROID 6.820E-14 1.446E-11 1.661E-11 1.180E-15-1.OOOE+00 3.920E-12 1.300E-12 REMAINDER 6.450E-14 1.471E-11 1.689E-11 1.200E-15-1.000E+00 2.900E-10 1.720E-09 EFFECTIVE 6.790E-14 1.532E-11 1.759E-11 1.250E-15-1.000E+00 1.700E-10 5.430E-10 SKIN(FGR) 8.560E-14 2.280E-11 2.618E-11 1.860E-15-1.000E+00 0.OOOE+00 0.OOOE+00 Y-90 GONADS 1.890E-16 1.586E-13 1.601E-12 5.750E-18-1.O0OE+00 5.170E-13 1.430E-14

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ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D28" (Next D29 Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21 C-1 03 0 Ref.

BREAST 2.200E-16 1.578E-13 1.593E-12 5.720E-18-1.OOOE+00 5.170E-13 1.270E-14 LUNGS 1.770E-16 1.313E-13 1.326E-12 4.760E-18-1.000E+00 9.310E-09 1.260E-14 RED MARR 1.620E-16 1.261E-13 1.273E-124.570E-18-1.000E+00 1.520E-11 3.700E-13 BONE SUR 4.440E-16 3.228E-13 3.259E-12 1.170E-17-1.000E+00 1.510E-11 3.670E-13 THYROID 1.870E-16 1.385E-13 1.398E-12 5.020E-18-1.000E+00 5.170E-13 1.260E-14 REMAINDER 1.680E-16 1.291E-13 1.303E-12 4,680E-18-1.000E+00 3.870E-09 9.680E-09 EFFECTIVE 1.900E-16 1.468E-13 1.482E-12 5.320E-18-1.000E+00 2.280E-09 2.910E-09 SKIN(FGR) 6.240E-14 2.897E-10 2.924E-09 1.050E-14-1.000E+00 0,000E+00 0.000E+00 Y-91 GONADS 2.560E-16 1.756E-13 3.546E-12 6.110E-18-1.000E+00 8.200E-12 3.540E-12 BREAST 2.930E-16 1.713E-13 3.459E-12 5.960E-18-1.000E+00 8.920E-12 5.540E-13 LUNGS 2,500E-16 1.526E-13 3.082E-12 5.310E-18-1.000E+00 9.870E-08 2.020E-13 RED MARR 2.410E-16 1.521E-13 3.070E-12 5.290E-18-1.000E+00 3.190E-10 6.590E-12 BONE SUR 4.560E-16 2.903E-13 5.862E-12 1.010E-17-1.000E+00 3.180E-10 6.130E-12 THYROID 2.600E-16 1.564E-13 3.157E-12 5.440E-18-1.000E+00 8.500E-12 1.290E-13 REMAINDER 2.390E-16 1.509E-13 3.047E-12 5.250E-18-1.000E+00 4.200E-09 8.570E-09 EFFECTIVE 2.600E-16 1-.650E-1 3 3.332E-1 2 5.740E-1 8-1.000E+00 1.320E-08 2.570E-09 SKIN(FGR) 3.850E-14 1.989E-10 4.016E-09 6.920E-15-1.000E+00 0.000E+00 O.000E+00 Y-92 GONADS 1.270E-14 3.855E-124.872E-12 2.650E-16-1.000E+00 2.610E-12 1.960E-11 BREAST 1.440E-14 3.680E-12 4.652E-12 2.530E-16-1.OOOE+00 1.500E-12 3.550E-12 LUNGS 1.270E-14 3.535E-12 4.468E-12 2.430E-16-1.000E+00 1.240E-09 1.390E-12 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-16-1.000E+00 1.510E-12 1.750E-12 THYROID 1.300E-14 3.579E-12 4.523E-12 2.460E-16-1.000E+00 1.050E-12 1.770E-13 REMAINDER 1.220E-14 3.506E-12 4.431E-12 2.410E-16-1.000E+00 2.030E-10 1.700E-09 EFFECTIVE 1.300E-14 3.680E-12 4.652E-12 2.530E-16-1.OOOE+00 2.110E-10 5.150E-10 SKIN(FGR) 1.140E-13 2.022E-10 2.556E-10 1.390E-14-1.000E+00 0.000E+00 0.000E+00 Y-93 GONADS 4.670E-15 2.108E-12 4.989E-12 9.510E-17-1.000E+00 5.310E-12 2.200E-11 BREAST 5.300E-15 2.026E-12 4.794E-12 9.140E-17-1.000E+Q0 1.740E-12 3.130E-12 LUNGS 4.680E-15 1.937E-12 4.585E-12 8.740E-17-1.000E+00 2.520E-09 8.670E-13 RED MARR 4.580E-15 1.972E-12 4.669E-12 8.900E-17-1.000E+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-124.516E-12 8.610E-17-1.000E+00 9.260E-13 1.260E-13 REMAINDER 4.510E-15 1.919E-12 4.543E-12 8.660E-17-1.OOOE+00 9.250E-10 4.090E-09 EFFECTIVE 4.800E-15 2.021 E-12 4.784E-12 9.120E-17-1.000E+00 5.820E-10 1.230E-09 SKIN(FGR) 8.500E-14 2.726E-10 6.452E-10 1.230E-14-1.OOOE+00 0.OOOE+00 O.000E+00 Zr-95 GONADS 3.530E-14 2.182E-11 4.421E-10 7.590E-16-1.000E+00 1.880E-09 8.160E-10 BREAST 4.010E-14 2.084E-11 4.223E-10 7.250E-16-1.000E+00 1.910E-09 1.050E-10 LUNGS 3.510E-14 1.989E-11 4.030E-10 6.920E-16-1.000E+00 2.170E-09 2.340E-11 RED MARR 3.430E-14 2.030E-11 4.112E-10 7.060E-16-1.OOOE+00 1.300E-08 2.140E-10 BONE SUR 5.620E-142.875E-11 5.824E-10 1.OOOE-15-1.OOOE+00 1.030E-074.860E-10 THYROID 3.610E-14 2.076E-11 4.205E-10 7.220E-16-1.OOOE+00 1.440E-09 8.270E-12 REMAINDER 3.360E-14 1.963E-1 1 3.978E-10 6.830E-16-1.OOOE+00 2.280E-09 2.530E-09 EFFECTIVE 3.600E-1 4 2.078E-11 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-11 5.190E-10 8.910E-16-1.OOOE+00 0.000E+00 0.OOOE+00

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

Zr-97 GONADS 8.800E-15 2.179E-11 7.799E-11 9.253E-16-1.OOOE+00 1.840E-10 6.228E-10 BREAST 9.990E-15 2.083E-11 7.455E-11 8.846E-16-1.OOOE+004.700E-118.137E-11 LUNGS 8.810E-151.992E-11 7.127E-11 8.456E-16-1.OOOE+00 4.110E-09 1.770E-11 RED MARR 8.640E-1 5 2.034E-1 1 7.279E-1 1 8.634E-1 6-1.OOOE+00 6.370E-11 1.302E-1 0 BONE SUR 1.380E-14 2.881E-11 1.031E-10 1.224E-15-1.000E+00 3.500E-11 4.558E-11 THYROID 9.030E-15 2.061E-11 7.377E-11 8.755E-16-1.OOOE+00 2.310E-11 2.671E-12 REMAINDER 8.480E-1 5 1.966E-1 1 7.035E-11 8.345E-1 6-1.OOOE+00 2.040E-09 6.990E-09 EFFECTIVE 4.432E-14 2.078E-11 7.438E-11 8.824E-16-1.000E+00 1.171E-09 2.283E-09 SKIN(FGR) 5.550E-14 2.281E-10 8.148E-10 9.587E-15-1.000E+00 0.000E+00 0.OOOE+00 Nb-95 GONADS 3.660E-14 2.253E-11 4.435E-10 7.850E-16-1.OOOE+00 4.320E-10 8.050E-10 BREAST 4.160E-14 2.150E-11 4.231E-10 7.490E-16-1.000E+00 4.070E-10 1.070E-10 LUNGS 3.650E-14 2.055E-11 4.045E-10 7.160E-16-1.000E+00 8.320E-09 2.740E-11 RED MARR 3.560E-14 2.101E-11 4.135E-10 7.320E-16-1.000E+004.420E-10 1.990E-10 BONE SUR 5.790E-14 2.957E-11 5.819E-10 1.030E-15-1.000E+00 5.130E-10 2.940E-10 THYROID 3.750E-14 2.144E-11 4.220E-10 7.470E-16-1.000E+00 3.580E-10 1.180E-11 REMAINDER 3.490E-14 2.032E-11 4.000E-10 7.080E-16-1.000E+00 1.070E-09 1.470E-09 EFFECTIVE 3.740E-14 2.147E-11 4.226E-10 7.480E-16-1.000E+00 1.570E-09 6.950E-10 SKIN(FGR) 4.300E-14 2.598E-11 5.112E-10 9.050E-16-1.000E+00 0.000E+00 0.OOOE+00 Mo-99 GONADS 7.130E-15 4.282E-1 2 4.403E-1 11.550E-16-1.000E+00 9.510E-1 1 2.180E-1 0 BREAST 8.130E-1 5 4.116E-1 2 4.233E-11 1.490E-1 6-1.OOOE+00 2.750E-11 3.430E-11 LUNGS 7.060E-15 3.867E-12 3.977E-11 1.400E-16-1.OOOE+00 4.290E-09 1.51OE-11 RED MARR 6.820E-1 5 3.923E-12 4.034E-1 11.420E-1 6-1.000E+00 5.240E-1 1 8.320E-11 BONE SUR 1.240E-14 6,105E-12 6.278E-11 2.21 OE-16-1.OOOE+00 4.130E-11 6.320E-1 1 THYROID 7.270E-15 4.033E-12 4.147E-1 11.460E-1 6-1.000E+00 1.520E-1 11.030E-1 1 REMAINDER 6.740E-15 3.812E-12 3.920E-11 1.380E-16-1.000E+00 1.740E-09 4.280E-09 EFFECTIVE 7.280E-15 4.061E-12 4.176E-11 1.470E-16-1.000E+00 1.070E-09 1.360E-09 SKIN(FGR) 3.140E-14 1.039E-10 1.068E-09 3.760E-15-1.OOOE+00 0.000E+00 0.000E+00 Tc-99m GONADS 5.750E-15 2.334E-12 3.877E-12 1.240E-16-1.OOOE+00 2.770E-12 9.750E-12 BREAST 6.650E-15 2.258E-12 3.752E-12 1.200E-16-1.000E+00 2.150E-12 3.570E-12 LUNGS 5.490E-15 2.127E-12 3.533E-12 1.130E-16-1.000E+00 2.280E-11 3.140E-12 RED MARR 4.910E-15 2.070E-12 3.439E-12 1.100E-16-1.000E+00 3.360E-12 6.290E-12 BONE SUR 1.630E-14 5.383E-12 8.942E-12 2.860E-16-1.OOOE+00 2.620E-12 4.060E-12 THYROID 5.750E-15 2.145E-12 3.564E-12 1.140E-16-1.000E+00 5.010E-11 8.460E-11 REMAINDER 5.150E-15 2.070E-12 3.439E-12 1.100E-16-1.OOOE+00 1.020E-11 3.340E-11 EFFECTIVE 5.890E-15 2.277E-12 3.783E-12 1.210E-16-1.000E+00 8.800E-12 1.680E-11 SKIN(FGR) 7.140E-1 5 2.71 GE-1 2 4.502E-1 2 1.440E-1 6-1.OOOE+00 0.OOOE+00 0.000E+00 Ru-103 GONADS 2.191E-14 1.404E-11 2.783E-104.892E-16-1.OOOE+00 3.070E-10 5.720E-10 BREAST 2.512E-14 1.350E-1 1 2.677E-10 4.705E-1 6-1.OOOE+00 3.110E-10 1.200E-10 LUNGS 2.180E-14 1.273E-11 2.522E-10 4,432E-1 6-1.000E+00 1.561 E-08 7.310E-11 RED MARR 2.100E-14 1.287E-11 2.551E-10 4.483E-16-1.OOOE+00 3.190E-10 1.660E-10 BONE SUR 3.892E-14 1.958E-11 3.882E-10 6.823E-16-1.000E+00 2.370E-10 9.631E-11 THYROID 2.241E-14 1.331E-11 2.639E-10 4.638E-16-1.OOOE+00 2.570E-10 6.250E-11 REMAINDER 2.080E-14 1.248E-11 2.472E-10 4.346E-16-1.000E+00 1.250E-09 2.110E-09

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EFFECTIVE 2.251 E-14 1.332E-1 1 2.641E-10 4.642E-16-1.000E+00 2.421E-09 8.271E-10 SKIN(FGR) 2.774E-14 1.785E-11 3.543E-10 6.229E-16-1.000E+00 0.OOOE+00 0.000E+00 Ru-105 GONADS 3.720E-14 1.327E-11 1.861E-11 8.070E-16-1.000E+00 1.590E-11 9.670E-11 BREAST 4.240E-14 1.271E-11 1.783E-11 7.730E-16-1.000E+00 6.610E-12 1.590E-11 LUNGS 3.700E-14 1.210E-11 1.697E-11 7.360E-16-1.OOOE+00 5.730E-10 6.210E-12 RED MARR 3.590E-14 1.230E-11 1.725E-11 7.480E-16-1.OOOE+00 7.700E-12 2.350E-11 BONE SUR 6.280E-14 1.809E-11 2.537E-11 1.100E-15-1.OOOE+00 4.620E-12 8.890E-12 THYROID 3.800E-14 1.260E-11 1.766E-11 7.660E-16-1.OOOE+00 4.150E-12 1.820E-12 REMAINDER 3.540E-14 1.189E-11 1.667E-11 7.230E-16-1.000E+00 1.610E-10 8.540E-10 EFFECTIVE 3.810E-14 1.265E-11 1.773E-11 7.690E-16-1.000E+00 1.230E-10 2.870E-10 SKIN(FGR) 6.730E-14 7.368E-11 1.033E-10 4.480E-15-1.000E+00 0.000E+00 0.000E+00 Ru-106 GONADS 1.O1OE-14 6.411E-12 1.340E-10 2.230E-16-1.OOOE+00 1.300E-09 1.640E-09 BREAST 1.160E-14 6.152E-121.286E-10 2.140E-16-1.000E+00 1.780E-09 1.440E-09 LUNGS 1.010E-14 5.836E-12 1.220E-10 2.030E-16-1.000E+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.OOOE+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.OOOE+00 1.200E-08 2.110E-08 EFFECTIVE 1.040E-14 6.095E-12 1.274E-10 2.120E-16-1.000E+00 1.290E-07 7.400E-09 SKIN(FGR) 1.090E-13 4.082E-10 8.531E-09 1.420E-14-1.0O0E+00 0.OOOE+00 0.000E+00 Rh-105 GONADS 3.640E-15 2.127E-12 1.411E-11 7.980E-17-1.OOOE+00 2.110E-11 5.800E-11 BREAST 4.160E-15 2.063E-12 1.369E-11 7.740E-17-1.OOOE+00 5.610E-12 8.970E-12 LUNGS 3.570E-1 5 1.935E-1 2 1.284E-1 1 7.260E-1 7-1.OOOE+00 9.580E-1 0 3.860E-1 2 RED MARR 3.380E-15 1.946E-12 1.291E-11 7.300E-17-1.OOOE+00 7.770E-12 1.470E-11 BONE SUR 7.530E-15 3.332E-12 2.210E-11 1.250E-16-1.OOOE+00 4.460E-12 6.750E-12 THYROID 3.680E-15 1.983E-12 1.316E-11 7.440E-17-1.OOOE+00 2.880E-12 2.910E-12 REMAINDER 3.390E-15 1.885E-12 1.250E-1 1 7.070E-17-1.OOOE+00 4.530E-10 1.270E-09 EFFECTIVE 3.720E-15 2.031E-12 1.347E-11 7.620E-17-1.000E+00 2.580E-10 3.990E-10 SKIN(FGR) 1.070E-14 4.691E-12 3.112E-1 11.760E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 Sb-127 GONADS 3.260E-14 1.985E-11 2.441E-107.100E-16-1.OOOE+00 2.520E-10 6.140E-10 BREAST 3.720E-14 1.904E-11 2.341E-10 6.810E-16-1.OOOE+00 9.120E-11 7.600E-11 LUNGS 3.240E-14 1.809E-11 2.224E-10 6.470E-16-1.OOOE+00 6.940E-09 1.570E-11 RED MARR 3.140E-14 1.834E-11 2.255E-106.560E-16-1.OOOE+00 1.610E-10 1.330E-10 BONE SUR 5.520E-14 2.720E-11 3.345E-10 9.730E-16-1.OOOE+00 1.340E-10 5.240E-11 THYROID 3.330E-14 1.884E-11 2.317E-10 6.740E-16-1.OOOE+00 6.150E-11 4.640E-12 REMAINDER 3.090E-14 1.775E-1 1 2.183E-1 0 6.350E-16-1.OOOE+00 2.330E-09 5.870E-09 EFFECTIVE 3.330E-14 1.890E-1 1 2.324E-10 6.760E-16-1.OOOE+00 1.630E-09 1.950E-09 SKIN(FGR) 5.580E-14 7.967E-1 19,799E-10 2.850E-15-1.000E+00 0.OOOE+00 0.000E+00 Sb-129 GONADS 6.970E-14 2.336E-11 3.231E-11 1.440E-15-1.OOOE+00 2.150E-11 1.510E-10 BREAST 7.910E-14 2.222E-11 3.074E-11 1.370E-15-1.000E+00 1.280E-11 2.560E-1I LUNGS 6.980E-14 2.141 E-1 1 2.962E-1 11.320E-15-1.OOOE+00 8.980E-10 9.390E-12 RED MARR 6.860E-14 2.190E-11 3.029E-1 1 1.350E-1 5-1,000E+00 1.700E-1 1 3.670E- 1I BONE SUR 1.070E-13 3.033E-1I 4.196E-1I 1.870E-15-1.OOOE+00 1.460E-11 1.340E-1I

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THYROID 7.160E-14 2.174E-11 3.007E-11 1.340E-15-1.OOOE+00 9.720E-12 1.470E-12 REMAINDER 6.710E-14 2.125E-11 2.939E-11 1.310E-15-1.OOOE+00 1.870E-10 1.450E-09 EFFECTIVE 7.140E-14 2.238E-11 3.096E-11 1.380E-15-1.OOOE+00 1.740E-10 4.840E-10 SKIN(FGR) 1.050E-13 8.273E-11 1.144E-10 5.100E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 Te-127 GONADS 2.370E-16 1.191E-13 2.661E-13 5.480E-18-1.OOOE+00 2.020E-12 4.020E-12 BREAST 2.730E-16 1.158E-13 2.588E-13 5.330E-18-1.OOOE+00 1.880E-12 3.OOOE-12 LUNGS 2.320E-16 1.060E-13 2.370E-13 4.880E-18-1.OOOE+00 4.270E-10 2.890E-12 RED MARR 2.210E-16 1.058E-13 2.365E-13 4.870E-18-1.OOOE+00 4.090E-12 6.570E-12 BONE SUR 4.650E-16 1.862E-13 4.162E-13 8.570E-18-1.OOOE+00 4.090E-12 6.460E-12 THYROID 2.400E-16 1.106E-13 2.472E-13 5.090E-18-1.OOOE+00 1.840E-12 2.860E-12 REMAINDER 2.210E-16 1.036E-13 2.316E-13 4.770E-18-1.OOOE+00 1.1 l0E-10 6.130E-10 EFFECTIVE 2.420E-16 1.125E-13 2.515E-13 5.180E-18-1.OOOE+00 8.600E-11 1.870E-10 SKIN(FGR) 1.140E-14 1.173E-11 2.622E-11 5.400E-16-1.OOOE+00 0.000E+00 0.OOOE+00 Te-127m GONADS 1.900E-16 4.689E-13 9.642E-12 1.630E-17-1.OOOE+00 1.1O0E-10 1.250E-10 BREAST 2.690E-16 5.150E-13 1.059E-11 1.790E-17-1.OOOE+Q0 1.100E-10 9.740E-11 LUNGS 7.620E-17 1.602E-13 3.295E-12 5.570E-18-1.OOOE+00 3.340E-08 9.620E-11 RED MARR 6.430E-17 1.249E-13 2.567E-12 4.340E-18-1.OOOE+00 5.360E-09 5.430E-09 BONE SUR 3.940E-16 9.005E-13 1.852E-11 3.130E-17-1.OOOE+00 2.040E-08 2.070E-08 THYROID 1.500E-1 6 2.779E-1 3 5.714E-1 2 9.660E-1 8-1.OOOE+00 9.660E-1 1 9.430E-1 1 REMAINDER 8.640E-17 1.999E-13 4.111E-12 6.950E-18-1.OOOE+00 1.660E-09 2.980E-09 EFFECTIVE 1.470E-16 3.251E-13 6.684E-12 1.130E-17-1.OOOE+00 5.810E-09 2.230E-09 SKIN(FGR) 8.490E-16 1.496E-12 3.076E-1 1 5.200E-1 7-1.OOOE+00 0.OOOE+00 O.OOOE+00 Te- 129 GONADS 2.710E-15 3.889E-13 3.922E-13 6.510E-17-1.OOOE+00 5.050E-13 1.590E-12 BREAST 3.120E-15 3.800E-13 3.832E-13 6.360E-17-1.OOOE+00 5,390E-13 6.050E-13 LUNGS 2.640E-15 3.298E-13 3.326E-13 5.520E-17-1.OOOE+00 1.530E-104.910E-13 RED MARR 2.540E-15 3.298E-13 3.326E-13 5.520E-17-1.OOOE+00 6.190E-13 7.640E-13 BONE SUR 4.880E-15 5.753E-13 5.802E-13 9.630E-17-1.OOOE+00 6.220E-13 5.400E-13 THYROID 2.740E-15 3.525E-13 3.555E-13 5.900E-17-1.000E+00 5.090E-13 3.360E-13 REMAINDER 2.520E-15 3.262E-13 3.289E-13 5.460E-17-1.OOOE+00 7.280E-12 1.790E-10 EFFECTIVE 2.750E-15 3.590E-13 3.621E-13 6.010E-17-1.OOOE+00 2.090E-11 5.450E-11 SKIN(FGR) 3.570E-14 3.429E-11 3.458E-11 5.740E-15-1.OOOE+00 0.000E+00 0.000E+00 Te-129m GONADS 1.560E-15 2.206E-12 4.799E-11 8.561E-17-1.OOOE+00 1.780E-10 2.420E-10 BREAST 1.810E-15 2.181E-12 4.739E-11 8.454E-17-1.OOOE+00 1.690E-10 1.664E-10 LUNGS 1.460E-15 1.741E-12 3.815E-11 6.808E-17-1.O0OE+00 4.030E-08 1.593E-10 RED MARR 1.420E-151.729E-12 3.793E-11 6.768E-17-1.OOOE+00 3.100E-09 3.500E-09 BONE SUR 2.600E-15 3.287E-12 7.147E-11 1.275E-16-1.OOOE+00 7.050E-09 7.990E-09 THYROID 1.560E-15 1.923E-12 4.201E-11 7.495E-17-1.000E+00 1.560E-10 1.572E-10 REMAINDER 1.410E-15 1.746E-12 3.822E-11 6.819E-17-1.000E+00 3.270E-09 7.196E-09 EFFECTIVE 3.337E-15 1.974E-12 4.308E-11 7.686E-17-1.000E+00 6.484E-09 2.925E-09 SKIN(FGR) 1.490E-14 1.501E-10 3.360E-09 6.001E-15-1.OOOE+00 0.000E+00 0.000E+00 Te-131m GONADS 6.850E-14 4.020E-1 1 2.343E-10 1.535E-15-1.000E+00 2.340E-10 7.415E-10 BREAST 7.780E-14 3.853E-11 2.246E-10 1.472E-15-1.OOOE+00 9.250E-11 1.361E-10 LUNGS 6.830E-14 3.657E-11 2.131 E-1 0 1.397E-1 5-1.OOOE+00 2.230E-09 6.335E-1 1

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

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RED MARR 6.680E-14 3.736E-11 2.178E-10 1.427E-15-1.OOOE+00 1.410E-10 2.435E-10 BONE SUR 1.090E-13 5.467E-11 3.189E-10 2.090E-15-1.OOOE+00 2.270E-10 3.248E-10 THYROID 7.020E-14 3.741E-11 2.181E-10 1.429E-15-1.QOOE+00 3.610E-08 4.383E-08 REMAINDER 6.550E-14 3.626E-11 2.113E-10 1.385E-15-1.OOE+00 9.460E-10 3.153E-09 EFFECTIVE 7.463E-14 3.825E-11 2.229E-10 1.461E-15-1.OO0E+00 1.758E-09 2.514E-09 SKIN(FGR) 8.850E-14 1.033E-10 6.188E-10 4.056E-15-1.OOOE+00 0.000E+00 0.OOOE+00 Te-132 GONADS 1.020E-14 6.812E-12 7.706E-11 2.450E-16-1.OOE+00 4.150E-10 5.410E-10 BREAST 1,180E-14 6.756E-12 7.643E-11 2.430E-16-1.OOOE+00 3.630E-10 3.500E-10 LUNGS 9.650E-15 5.727E-12 6.479E-11 2.060E-16-1.OOOE+00 1.670E-09 3.300E-10 RED MARR 8.950E-15 5.588E-12 6.322E-11 2.010E-16-1.OOOE+00 4.270E-10 4.440E-10 BONE SUR 2.420E-14 1.273E-11 1.441E-10 4.580E-16-1.OOOE+00 7.120E-10 8.300E-10 THYROID 1.020E-14 5.978E-12 6.762E-11 2.150E-16-1.OOOE+00 6.280E-08 5.950E-08 REMAINDER 9.160E-15 5.644E-12 6.385E-1 1 2.030E-16-1.000E+00 7.890E-1Q1 .490E-09 EFFECTIVE 1.030E-14 6.339E-12 7.171E-11 2.280E-16-1.OOOE+00 2.550E-09 2.540E-09 SKIN(FGR) 1.390E-14 8.313E-12 9.405E-1 1 2.990E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 1-131 GONADS 1.780E-14 1.119E-11 1.789E-10 3.940E-16-1.OOOE+00 2.530E-11 4.070E-11 BREAST 2.040E-14 1.082E-11 1.730E-10 3.810E-16-1.OOOE+00 7.880E-11 1.210E-10 LUNGS 1.760E-14 1.016E-11 1.626E-10 3.580E-16-1.OOOE+00 6.570E-10 1.020E-10 RED MARR 1.680E-14 1.022E-11 1.635E-10 3.600E-16-1.OOOE+00 6.260E-11 9.440E-11 BONE SUR 3.450E-14 1.675E-11 2.679E-10 5.900E-16-1.000E+00 5.730E-11 8.720E-11 THYROID 1.81 GE-1 4 1.053E-1 11.685E-1 0 3.71 GE-1 6-1.000E+00 2.920E-07 4.760E-07 REMAINDER 1.670E-14 9.908E-12 1.585E-10 3.490E-16-1.000E+00 8.030E-11 1.570E-10 EFFECTIVE 1.820E-14 1.067E-11 1.707E-10 3.760E-16-1.000E+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 0.000E+00 0.000E+00 1-132 GONADS 1.090E-13 2.523E-11 2.771E-11 2.320E-15-1.OOE+00 9.950E-12 2.330E-11 BREAST 1.240E-13 2.414E-11 2.652E-11 2.220E-15-1.000E+00 1.410E-11 2.520E-11 LUNGS 1.090E-13 2.305E-11 2.532E-11 2.120E-15-1.OOOE+00 2.710E-10 2.640E-11 RED MARR 1.070E-13 2.360E-11 2.592E-11 2.170E-15-1.000E÷00 1.400E-11 2.460E-11 BONE SUR 1.730E-13 3.327E-11 3.655E-11 3.060E-15-1.000E+00 1.240E-11 2.190E-11 THYROID 1.120E-13 2.381E-11 2.616E-11 2.190E-15-1.000E+00 1.740E-09 3.870E-09 REMAINDER 1.050E-13 2.283E-11 2.509E-11 2.100E-15-1.000E+00 3.780E-11 1.650E-10 EFFECTIVE 1.120E-13 2.403E-11 2.640E-11 2.210E-15-1.000E+00 1.030E-10 1.820E-10 SKIN(FGR) 1.580E-13 8.199E-1 1 9.007E-1 1 7.540E-1 5-1.000E+00 0.000E+00 0.000E+00 1-133 GONADS 2.870E-14 1.585E-11 6.748E-11 6.270E-16-1.OOOE+00 1.950E-11 3.630E-11 BREAST 3.280E-14 1.519E-11 6.468E-11 6.010E-16-1.000E+00 2.940E-11 4.680E-11 LUNGS 2.860E-14 1.446E-11 6.156E-11 5.720E-16-1.000E+008.200E-104.530E-11 RED MARR 2.770E-14 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-14 2.161E-11 9.202E-11 8.550E-16-1.000E+00 2.520E-11 4.070E-11 THYROID 2.930E-14 1.502E-11 6.393E-11 5.940E-16-1.000E+00 4.860E-08 9.100E-08 REMAINDER 2.730E-14 1.418E-11 6.038E-11 5.610E-16-1.0O0E+00 5.000E-11 1.550E-10 EFFECTIVE 2.940E-14 1.509E-11 6.425E-11 5.970E-16-1.0O0E+00 1.580E-09 2.800E-09 SKIN(FGR) 5.830E-14 1.150E-10 4.897E-10 4.550E-15-1.000E+00 0.000E+00 0.000E+00 1-134 GONADS 1.270E-13 1.200E-11 1.202E-11 2.640E-15-1.OOOE+00 4.250E-12 1.100E-11

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BREAST 1.440E-13 1.145E-1 11.147E-1 1 2.520E-1 5-1.0OOE+00 6.170E-12 1.170E-1 1 LUNGS 1.270E-1 31 1OOE-1 11.1 02E-1 1 2.420E-1 5-1 000E+00 1,430E-1 0 1.260E-1 1 RED MARR 1.250E-13 1.127E-11 1.129E-11 2.480E-15-1.OOOE+00 6.080E-12 1.090E-11 BONE SUR 1.960E-13 1.568E-11 1.571E-11 3.450E-15-1.OOOE+00 5.310E-12 9.320E-12 THYROID 1.300E-13 1.127E-1 11.129E-1 1 2.480E-15-1.OOOE+00 2.880E-10 6.210E-10 REMAINDER 1.220E-13 1.091E-11 1.093E-11 2.400E-15-1.QOOE+00 2.270E-11 1.340E-10 EFFECTIVE 1.300E-13 1.150E-11 1.152E-11 2.530E-15-1.OOOE+00 3.550E-11 6.660E-11 SKIN(FGR) 1.870E-13 4.477E-11 4.485E-11 9.850E-15-1.OOOE+00 0.0OOE+00 0.O0OE+00 1-135 GONADS 8.078E-14 3.113E-11 5.489E-11 1.599E-15-1.OOOE+00 1.700E-11 3.610E-11 BREAST 9.143E-14 2.971E-11 5.240E-11 1.526E-15-1.OOOE+00 2.340E-11 3.850E-11 LUNGS 8.145E-14 2.886E-11 5.089E-11 1.482E-15-1.OOOE+00 4.410E-10 3.750E-11 RED MARR 8.054E-14 2.965E-11 5.228E-11 1,523E-15-1,OOOE+00 2.240E-11 3.650E-11 BONE SUR 1.184E-13 3.983E-11 7.024E-11 2.046E-15-1.OOOE+00 2.010E-11 3.360E-11 THYROID 8.324E-14 2.852E-1 1 5.030E-11 1.465E-15-1.000E+00 8.460E-09 1.790E-08 REMAINDER 7.861 E-14 2.883E-1 1 5.084E-1 11.481 E-1 5-1.OOOE+00 4.700E-1 11.540E-1 0 EFFECTIVE 8.294E-14 2.989E-11 5.271E-11 1.535E-15-1.000E+00 3.320E-10 6.080E-10 SKIN(FGR) 1.156E-13 9.826E-11 1.733E-10 5.047E-15-1.OOOE+00 0.000E+00 0.OOOE+00 Xe-133 GONADS 1.61 0E-15 1.465E-1 2 2.052E-1 1 5.200E-1 7-1.OOE+00 0.OOOE+00 0.OOOE+00 BREAST 1.960E-1 5 1.505E-1 2 2.107E-1 1 5.340E-1 7-1.OOOE+00 0.OOOE+00 O.OOOE+00 LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-1.OOOE+00 0.OOOE+00 0.OOOE+00 RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+00 O.OOOE+00 0.OOOE+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.OOOE+00 0.000E+00 0.OOOE+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OOOE+00 0.OOOE+00 0.000E+00 REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-1.000E+00 0.000E+00 O.000E+00 EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-1.OOOE+00 0.000E+00 O.OOE+00 SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOOE+00 0.OO0E+00 0.OOOE+00 Xe-133m GONADS 1.61 0E-15 1.465E-1 2 2.052E-1 1 5.200E-1 7-1.0OOE+00 0.OOOE+00 0.OOOE+00 BREAST 1.960E-15 1.505E-12 2.107E-1 1 5.340E-17-1.OOOE+00 O.OOOE+00 0.OOOE+00 LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-1.OOOE+00 G.OOOE+00 0.OOOE+00 RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+00 0.OOOE+00 0.OOOE+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.0OOE+00 0.OOOE+00 0.OOOE+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OOOE+00 0.OOOE+00 0.OOOE+00 REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-1.OOOE+00 0.OO0E+00 0.OOOE+00 EFFECTIVE 1.370E-15 1.299E-12 1.819E-11 4.610E-17-1.,OOE+00 0.OOOE+00 0.0OOE+00 SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOOE+00 O.OOOE+00 O.OOOE+00 Xe-135 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.0OOE+00 0.OOE+00 0.OOE+00 LUNGS 1.130E-14 4.959E-12 1.086E-1 1 2.300E-16-1.OOOE+00 0.OOOE+00 O.000E+00 RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-1.OOOE+00 O.OOOE+00 0.OOOE+00 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.OQOE+00 0.OOOE+00 0.000E+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.OOOE+00 D.OOOE+00 0.OOOE+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.OOOE+00 O.0OOE+0O 0.OOOE+00 SKIN(FGR) 3.120E-14 4.506E-1 1 9.867E-1 12.090E-15-1.OOOE+00 0.0OOE+00 0.000E+00

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Project:Nine Mile Point Nuclear Station Unit: 2 Disposition:

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Xe-135m GONADS 2.OOOE-14 5.933E-13 5.933E-134.480E-16-1.000E+00 0.OOOE+00 0.000E+00 BREAST 2.290E-14 5.695E-13 5.695E-13 4.300E-16-1.000E+00 0.000E+00 0.000E+00 LUNGS 1.980E-14 5.351E-13 5.351E-13 4.040E-16-1.000E+00 0.OOOE+00 0.000E+00 RED MARR 1.910E-14 5.404E-13 5.404E-13 4.080E-16-1.000E+00 0.OOOE+00 0.000E+00 BONE SUR 3.500E-14 8.251E-13 8.251E-13 6.230E-16-1.OOOE+00 0.OOOE+00 0.000E+00 THYROID 2.040E-14 5.615E-13 5,615E-13 4.240E-16-1.000E+00 0.000E+00 0.000E+00 REMAINDER 1.890E-14 5.245E-13 5.245E-13 3.960E-16-1.OOOE+00 0.OOOE+00 0.000E+00 EFFECTIVE 2.040E-14 5.615E-13 5.615E-13 4.240E-16-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 2.970E-14 1.867E-12 1.867E-12 1.410E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 Xe-138 GONADS 5.590E-14 1.315E-12 1.315E-12 1.070E-15-1.OOOE+00 0.000E+00 0.OOOE+00 BREAST 6.320E-14 1.254E-12 1.254E-12 1.020E-15-1.000E+00 0.000E+00 0.OOOE+00 LUNGS 5.660E-14 1.225E-12 1.225E-12 9.970E-16-1.OOOE+00 0.OOOE+00 0.OOOE+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-14 1.733E-12 1.733E-12 1.410E-15-1.000E+00 0.000E+00 0.000E+00 THYROID 5.770E-14 1.174E-12 1.174E-12 9.550E-16-1.OOOE+00 0.000E+00 0.000E+00 REMAINDER 5.490E-14 1.222E-12 1,222E-12 9.940E-16-1.OOOE+00 0.000E+00 0.000E+00 EFFECTIVE 5.770E-1 4 1.266E-12 1.266E-12 1.030E-15-1.000E+00 0.OOOE+00 0.000E+00 SKIN(FGR) 1.070E-13 9.403E-12 9.403E-12 7.650E-15-1.000E+00 0.000E+00 0.OOOE+00 Cs-1 34 GONADS 7.400E-14 4.607E-11 9.646E-10 1.600E-15-1.000E+00 1.300E-082.060E-08 BREAST 8.430E-144.406E-11 9.224E-10 1.530E-15-1.OOOE+00 1.080E-08 1.720E-08 LUNGS 7.370E-144.204E-11 8.802E-10 1.460E-15-1.OOOE+00 1.180E-08 1.760E-08 RED MARR 7.190E-14 4.262E-11 8.922E-10 1.480E-15-1.000E+00 1.180E-08 1.870E-08 BONE SUR 1.200E-13 6.105E-11 1.278E-09 2.120E-15-1.000E+00 1.100E-08 1.740E-08 THYROID 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.000E+00 1.110E-08 1.760E-08 REMAINDER 7.060E-14 4.147E-11 8.681E-10 1.440E-15-1.000E+00 1.390E-08 2.210E-08 EFFECTIVE 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.000E+00 1.250E-08 1.980E-08 SKIN(FGR) 9.450E-14 6.249E-11 1.308E-09 2.170E-15-1.000E+00 0.000E+00 0.000E+00 Cs-1 36 GONADS 1.040E-13 6.223E-11 1.102E-09 2.180E-15-1.000E+00 1.880E-09 3.040E-09 BREAST 1.180E-13 5.966E-11 1.056E-09 2.090E-15-1.000E+00 1.670E-09 2.650E-09 LUNGS 1.040E-13 5.710E-11 1.011E-09 2.000E-15-1.000E+00 2.320E-09 2.620E-09 RED MARR 1.010E-13 5.824E-11 1.031E-09 2,040E-15-1.000E+00 1.860E-09 2.950E-09 BONE SUR 1.660E-13 8.422E-11 1.491E-09 2.950E-15-1.000E+00 1.700E-09 2.710E-09 THYROID 1.070E-13 5.852E-11 1.036E-09 2.050E-15-1.000E+00 1.730E-09 2.740E-09 REMAINDER 9.950E-14 5.652E-11 1.001E-09 1.980E-15-1.000E+00 2.190E-09 3.520E-09 EFFECTIVE 1.060E-13 5.966E-11 1,056E-09 2.090E-15-1,000E+00 1.980E-09 3.040E-09 SKIN(FGR) 1.250E-13 7.251E-11 1.284E-09 2.540E-15-1.000E+00 0.000E+00 0.000E+00 Cs-137 GONADS 2.669E-14 1.669E-11 3.530E-10 5.840E-16-1.000E+00 8.760E-09 1.390E-08 BREAST 3.047E-14 1.596E-11 3.376E-10 5.585E-16-1.000E+00 7.840E-09 1.240E-08 LUNGS 2.649E-14 1.517E-11 3.209E-10 5.309E-16-1.000E+00 8.820E-09 1.270E-08 RED MARR 2.583E-14 1.542E-11 3.260E-10 5.394E-16-1.000E+00 8.300E-09 1.320E-08 BONE SUR 4.382E-14 2.238E-11 4.734E-10 7.832E-16-1.000E+00 7.940E-09 1.260E-08 THYROID 2.725E-14 1.588E-11 3.358E-10 5.556E-16-1.000E+00 7.930E-09 1.260E-08 REMAINDER 2.536E-14 1.490E-11 3.152E-10 5.215E-16-1.000E+00 9.120E-09 1.450E-08

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21 C-1 03 0 Ref.

EFFECTIVE 2.725E-14 1.585E-11 3.353E-10 5.546E-16-1.OOOE+00 8.630E-09 1.350E-08 SKIN(FGR) 4.392E-14 5.253E-1 11.11 0E-09 1.836E-1 5-1.OOOE+00 0.000E+00 0.000E+00 Ba-139 GONADS 2.130E-15 3.368E-13 3.429E-13 4.790E-17-1.OOOE+00 2.560E-12 1.560E-12 BREAST 2.450E-15 3.297E-13 3.357E-13 4.690E-17-1.OOOE+00 2.460E-12 5.170E-13 LUNGS 2.030E-1 5 3.002E-1 3 3.057E-1 3 4.270E-1 7-1.OOOE+00 2.530E-1 0 3.890E-1 3 RED MARR 1.870E-15 2.932E-13 2.985E-13 4.170E-17-1.OOOE+00 3.410E-12 8.590E-13 BONE SUR 5.290E-15 6.841E-13 6.965E-13 9.730E-17-1.OOOE+00 2.490E-12 4.380E-13 THYROID 2.130E-15 3.044E-13 3.100E-13 4,330E-17-1.OOOE+00 2.400E-12 2.660E-13 REMAINDER 1.920E-15 2.932E-13 2.985E-13 4.170E-17-1.OOE+00 4.820E-11 3.570E-10 EFFECTIVE 2.170E-15 3.227E-13 3.286E-13 4.590E-17-1.OOOE+00 4.640E-11 1.080E-10 SKIN(FGR) 6.160E-14 7.241E-11 7.373E-11 1.030E-14-1.OOOE+00 0.OOOE+00 0.OOOE+00 Ba-140 GONADS 8.410E-15 5.451E-12 9.607E-11 1.910E-16-1.OOOE+00 4.300E-10 9.960E-10 BREAST 9.640E-15 5.280E-12 9.305E-11 1.850E-16-1,OOOE+00 2,870E-10 1.590E-10 LUNGS 8.270E-1 5 4.852E-1 2 8.550E-1 11.700E-1 6-1.OOOE+00 1.660E-09 6.630E-1 1 RED MARR 7.930E-15 4.880E-12 8.601E-1 1 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.OOOE+00 2.410E-09 5.530E-10 THYROID 8.530E-15 5.109E-12 9.003E-11 1.790E-16-1.OOOE+00 2.560E-10 5.250E-11 REMAINDER 7.890E-15 4.766E-12 8.399E-11 1.670E-16-1.000E+00 1.410E-09 7.370E-09 EFFECTIVE 8.580E-1 5 5.137E-1 2 9.053E-1 11.800E-1 6-1.OOOE+00 1.01 OE-09 2.560E-09 SKIN(FGR) 2.520E-14 5.565E-11 9.808E-10 1.950E-15-1.000E+00 0.000E+00 0.OOOE+00 La-140 GONADS 1.140E-13 6.027E-11 4.425E-10 2.240E-15-1.OOOE+00 4.540E-10 1.340E-09 BREAST 1.290E-1 3 5.758E-1 1 4.228E-1 0 2.140E-1 5-1.OOOE+00 1.450E-1 0 1.800E-1 0 LUNGS 1.150E-13 5.596E-1 1 4.109E-1 0 2.080E-15-1.OOOE+00 4.210E-09 4.01OE-1 1 RED MARR 1.140E-13 5.731E-11 4.208E-10 2.130E-15-1.OOOE+00 2.140E-10 2.810E-10 BONE SUR 1.690E-13 7.776E-11 5.709E-10 2.890E-15-1.OOOE+00 1.410E-10 9.770E-11 THYROID 1.180E-13 5.462E-11 4.010E-10 2.030E-15-1.000E+00 6.870E-11 6.400E-12 REMAINDER 1.110E-13 5.569E-11 4.089E-10 2.070E-15-1.OOOE+00 2.120E-09 6.260E-09 EFFECTIVE 1.170E-13 5.812E-11 4.267E-10 2.160E-15-1.OOOE+00 1.310E-09 2.280E-09 SKIN(FGR) 1,660E-13 2.217E-10 1.628E-09 8.240E-15-1.OOOE+00 0.OOOE+00 0.OOOE+00 La-141 GONADS 2.330E-1 5 7.315E-1 3 9.675E-1 3 4.740E-1 7-1,OOOE+00 1.01 OE-1 1 3.770E-1 2 BREAST 2.640E-15 7.007E-13 9.267E-13 4.540E-17-1.OOOE+00 9.840E-12 7.070E-13 LUNGS 2.340E-15 6.713E-13 8.879E-13 4.350E-17-1.OOOE+00 6.460E-10 2.720E-13 RED MARR 2.310E-15 6.852E-13 9.063E-13 4.440E-17-1.000E+00 2.930E-11 1.070E-12 BONE SUR 3.490E-15 9.923E-13 1.312E-12 6.430E-17-1.OOOE+00 1.200E-10 6.060E-13 THYROID 2,390E-15 6.590E-13 8.716E-13 4.270E-17-1.OOOE+00 9.400E-12 5.290E-14 REMAINDER 2.260E-1i5 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-15 7.007E-13 9.267E-13 4.540E-17-1.OOOE+00 1.570E-10 3.740E-10 SKIN(FGR) 6.580E-14 1.667E-10 2.204E-10 1.080E-14-1.OOOE+00 0.OOOE+00 0.OOOE+00 La-142 GONADS 1.400E-13 1.978E-11 2.034E-11 2.540E-15-1.OOOE+00 1.660E-11 6.990E-11 BREAST 1.570E-13 1.885E-11 1.938E-11 2.420E-15-1.OOOE+00 1.130E-11 1.540E-11 LUNGS 1.420E-13 1,846E-11 1.898E-11 2.370E-15-1.OOOE+00 3.010E-10 8.400E-12 RED MARR 1.420E-13 1.900E-11 1.954E-11 2.440E-15-1.OOOE+00 1.360E-11 1.930E-11 BONE SUR 1.950E-13 2.484E-11 2.554E-11 3.190E-15-1.000E+00 1.110E-11 7.400E-12

t

~1 ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D36 (Next D377)

Project: Nine Mile Point Nuclear Station Unit: 2 Disposition:

Orginator/Date Reviewer/Date Calculation No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 THYROID 1.450E-131.768E-11 1.81BE-11 2.270E-15-1.OOOE+00 8.740E-12 1,160E-12 REMAINDER 1.380E-13 1.853E-11 1.906E-11 2.380E-15-1.OOOE+00 8.070E-11 5.200E-10 EFFECTIVE 1.440E-13 1.916E-11 1.970E-11 2.460E-15-1.DOE+00 6.840E-11 1.790E-10 SKIN(FGR) 2.160E-13 9.111E-11 9.368E-11 1.170E-14-1.OOOE+00 0.OOOE+00 0.OOOE+00 Ce-141 GONADS 3.380E-15 2.213E-12 4.332E-11 7.710E-17-1.OOOE+00 5.540E-11 1.080E-10 BREAST 3.930E-15 2.170E-124.247E-11 7.560E-17-1.0OOE+004.460E-11 1.110E-11 LUNGS 3.170E-15 1.951E-12 3.820E-11 6.800E-17-1.OOOE+00 1.670E-08 1.430E-12 RED MARR 2.830E-15 1.860E-12 3.641E-11 6.480E-17-1.O0E+00 8.960E-11 3.390E-11 BONE SUR 9.410E-15 5.166E-12 1.011E-10 1.800E-16-1.OOOE+00 2.540E-10 2.300E-11 THYROID 3.350E-15 2.003E-12 3.922E-11 6.980E-17-1.OOOE+00 2.550E-1 I 1.800E-13 REMAINDER 2.980E-15 1.894E-12 3.708E-11 6.600E-17-1.OOOE+00 1.260E-09 2.500E-09 EFFECTIVE 3.430E-15 2.118E-12 4.146E-1 1 7.380E-17-1.000E+00 2.420E-09 7.830E-10 SKIN(FGR) 1.020E-14 3.788E-1 2 7.416E-1 11.320E-16-1.OOOE+00 O.OOOE+00 0,OOOE+00 Ce-143 GONADS 1.280E-14 7.900E-1 2 4.958E-1 1 2.980E-1 6-1.OOOE+00 7.530E-11 2.120E-1 0 BREAST 1.470E-14 7.688E-1 2 4.825E-1 1 2.900E-1 6-1.OOOE+00 1.660E-1 I 2.320E-1 1 LUNGS 1.230E-14 6.893E-12 4.325E-11 2.600E-16-1.OOOE+00 3.880E-09 3.820E-12 RED MARR 1.170E-14 6.787E-12 4.259E-11 2.560E-16-1.OOOE+00 2.960E-11 5.070E-11 BONE SUR 2.520E-14 1.323E-11 8.302E-11 4.990E-16-1.OOE+00 1.640E-11 1.610E-11 THYROID 1.280E-1 4 7.211 E-1 2 4.525E-1 1 2.720E-1 6-1.OOOE+00 6.230E-1 2 4.350E-1 3 REMAINDER 1.170E-14 6.734E-12 4.226E-1 1 2.540E-1 6-1.OOOE+00 1.420E-09 3.890E-09 EFFECTIVE 1.290E-14 7.396E-12 4.642E-1 1 2.790E-16-1.OOE+00 9.160E-10 1.230E-09 SKIN(FGR) 3.960E-14 1.058E-10 6.638E-10 3.990E-15-1.OOOE+00 0.OOOE+00 O.000E+00 Ce-144 GONADS 2.725E-15 6.328E-13 1.319E-11 6.088E-17-1.000E+00 2.390E-10 6.987E-11 BREAST 3.129E-1 5 6.274E-13 1.307E-1 1 5.922E-1 7-1.000E+00 3.480E-10 1.223E-1 1 LUNGS 2.639E-15 5.228E-13 1.089E-1 1 5.362E-17-1.000E+00 7.911 E-07 6.551 E-1 2 RED MARR 2.507E-15 4.755E-13 9.907E-12 5.247E-17-1.000E+00 2.880E-09 8.923E-11 BONE SUR 5.441E-15 1.646E-12 3.429E-11 1.127E-16-1.000E+00 4.720E-09 1.280E-10 THYROID 2.753E-15 5.529E-13 1.152E-11 5.418E-17-1.000E+00 2.920E-10 5.154E-12 REMAINDER 2.534E-15 5.086E-13 1.060E-11 5.283E-17-1.000E+00 1.910E-08 1.890E-08 EFFECTIVE 2.773E-15 5.909E-13 1.231E-11 5.766E-17-1.OOE+00 1.010E-07 5.711E-09 SKIN(FGR) 8.574E-14 7,648E-13 1.594E-1 11,250E-14-1.000E+00 0.000E+00 0.000E+00 Pr-143 GONADS 2.130E-17 2.264E-14 4.032E-13 7.930E-19-1.000E+00 4.370E-18 8.990E-18 BREAST 2.550E-17 2.330E-14 4.149E-13 8.160E-19-1.000E+00 2.220E-18 1.090E-18 LUNGS 1.860E-17 1.642E-14 2.923E-13 5.750E-19-1.000E+00 1.330E-08 1.910E-19 RED MARR 1.620E-17 1.493E-14 2.659E-13 5.230E-19-1.000E+00 1.480E-11 1.030E-12 BONE SUR 5.930E-17 5.454E-14 9.711E-13 .1.910E-18-1.000E+00 1.490E-11 1.030E-12 THYROID 2.050E-17 1.802E-14 3.208E-13 6.310E-19-1.000E+00 1.680E-18 2.660E-20 REMAINDER 1.760E-17 1.642E-14 2.923E-13 5.750E-19-1.000E+00 1.970E-09 4.220E-09 EFFECTIVE 2.100E-17 2.002E-14 3.564E-13 7.010E-19-1.000E+00 2.190E-09 1.270E-09 SKIN(FGR) 1.760E-14 5.711E-1 11.017E-09 2.000E-15-1.000E+00 0.000E+00 0.000E+00 Nd-147 GONADS 6.130E-15 4.218E-12 7.235E-111 1.480E-16-1.000E+00 8.410E-1 1 1.790E-10 BREAST 7.120E-15 4.132E-12 7.088E-11 1.450E-16-1.000E+00 3.450E-11 1.870E-11 LUNGS 5.820E-15 3.648E-12 6.257E-1I 1.280E-16-1.000E+00 1.060E-08 2.440E-12

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D37 (Next D38 Project:Nine Mile Point Nuclear Station Unit: 2 Disposition: -

Originator/Date Reviewer/Date Calculaton No. Revision J. Metcalf 5/29/2007 Appendix E H21C-103 0 Ref.

RED MARR 5.400E-15 3.505E-12 6.013E-11 1.230E-16-1.OOOE+00 9.190E-11 5.050E-11 BONE SUR 1.320E-14 8.265E-12 1.418E-10 2.900E-16-1.OOOE+00 3.260E-10 2.220E-11 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-15 3.562E-12 6.111E-11 1.250E-16-1.OOOE+00 1.760E-09 3.760E-09 EFFECTIVE 6.190E-15 3.961E-12 6.795E-11 1.390E-16-1.OOE+00 1.850E-09 1.180E-09 SKIN(FGR) 1.950E-14 3.135E-11 5.377E-10 1.100E-15-1.OOE+00 0.000E+00 0.000E+00 Np-239 GONADS 7.530E-15 4.691E-12 4.380E-11 1.710E-16-1.000E+00 7.450E-11 1.620E-10 BREAST 8.730E-15 4.636E-12 4.329E-11 1.690E-16-1.000E+00 1.630E-11 1.720E-11 LUNGS 7.180E-15 4.115E-12 3.842E-11 1.500E-16-1.000E+00 2.360E-09 2.400E-12 RED MARR 6.500E-15 4.005E-12 3.740E-1 11.460E-16-1.000E+00 2.080E-10 4.660E-1 1 BONE SUR 2.000E-14 1.001E-11 9.349E-11 3.650E-16-1.000E+00 2.030E-09 3.590E-11 THYROID 7.520E-15 4.197E-12 3.919E-11 1.530E-16-1.000E+00 7.620E-12 2.070E-13 REMAINDER 6.760E-15 4.005E-12 3.740E-1 11.460E-16-1.000E+00 9,590E-10 2.770E-09 EFFECTIVE 7.690E-15 4.471E-12 4.175E-11 1.630E-16-1.000E+00 6.780E-10 8.820E-10 SKIN(FGR) 1.600E-14 7.215E-12 6.737E-1 1 2.630E-16-1.000E+00 0.000E+00 0.000E+00 Pu-238 GONADS 6.560E-18 4.291E-14 9.011E-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-18-1.000E+00 4.400E-10 1.800E-13 LUNGS 1.060E-1 8 2.267E-1 5 4.759E-1 4 7.870E-20-1.000E+00 3.200E-04 8.640E-1 4 RED MARR 1.680E-18 5.587E-15 1.173E-13 1.940E-19-1.000E+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 4.010E-18 9.792E-15 2.056E-13 3.400E-19-1.000E+00 3.860E-10 7.990E-14 REMAINDER 1.990E-18 9.216E-15 1.935E-13 3.200E-19-1.000E+00 2.740E-05 2.180E-08 EFFECTIVE 4.880E-18 2.413E-14 5.068E-13 8.380E-19-1.000E+00 7.790E-05 1.340E-08 SKIN(FGR) 4.090E-17 2.776E-13 5.830E-12 9.640E-18-1.000E+00 0.000E+00 0.000E+00 Pu-239 GONADS 4.840E-18 1.768E-14 3.713E-13 6.140E-19-1.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-18 2.267E-15 4,760E-14 7.870E-20-1.000E+00 3.230E-04 7.890E-14 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-19-1.000E+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-18 4.838E-15 1.016E-13 1.680E-19-1.000E+00 3.020E-05 2.120E-08 EFFECTIVE 4.240E-18 1.057E-14 2.220E-13 3.670E-19-1.000E+00 8.330E-05 1.400E-08 SKIN(FGR) 1.860E-17 1.057E-13 2.220E-12 3.670E-18-1.000E+00 0.000E+00 0.000E+00 Pu-240 GONADS 6.360E-18 4.118E-14 8.649E-13 1.430E-18-1.000E+00 1.200E-05 2.640E-09 BREAST 1.230E-17 5.328E-14 1.119E-12 1.850E-18-1.OOOE+00 4.330E-10 1.730E-13 LUNGS 1.090E-18 2.249E-15 4.723E-14 7.810E-20-1.000E+00 3.230E-04 8.220E-14 RED MARR 1.650E-18 5.386E-15 1.131E-13 1.870E-19-1.000E+00 6.570E-05 1.410E-08 BONE SUR 9.260E-18 3.398E-14 7.137E-13 1.180E-18-1.000E+00 8.210E-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-18 8.870E-15 1.863E-13 3.080E-19-1.OOOE+00 3.020E-05 2.130E-08 EFFECTIVE 4.750E-18 2.313E-14 4.857E-13 8.030E-19-1.000E+00 8.330E-05 1.400E-08

• SKIN(FGR) 3.920E-17 2.644E-13 5.552E-12 9.180E-18-1.000E+00 0.000E+00 0.000E+00 Pu-241 GONADS 7.190E-20 6.653E-17 1.396E-15 2.310E-21-1.000E+00 2.760E-07 5.660E-11

I f" ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page D38 (Next _D39 -)

Project-Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date No. Revision RCalculaon J. Metcalf 5/29/2007 Appendix E H21C-103 0 BREAST 8.670E-20 7.229E-17 1.517E-15 2.510E-21-1.000E+00 2.140E-11 2.790E-15 LUNGS 6.480E-20 4.090E-17 8.584E-16 1.420E-21-1.000E+00 3.180E-06 4.480E-15 RED MARR 5.630E-20 4.003E-17 8.403E-16 1.390E-21-1.000E+00 1.430E-06 2.780E-10 BONE SUR 2.190E-19 1.385E-16 2.908E-15 4.810E-21-1.OOE+00 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-17 9.007E-16 1.490E-21-1.000E+00 6.020E-07 1.850E-1 0 EFFECTIVE 7.250E-20 5.558E-17 1.167E-15 1.930E-21-1.OOOE+00 1.340E-06 2.070E-10 SKIN(FGR) 1.170E-19 2.033E-16 4.268E-15 7.060E-21-1.000E+00 0.000E+00 0.OOOE+00 Am-241 GONADS 8.580E-16 9.360E-131.966E-11 3.250E-17-1.000E+00 3.250E-05 2.700E-07 BREAST 1.070E-15 1.014E-12 2.129E-11 3.520E-17-1.000E+00 2.670E-09 2.620E-11 LUNGS 6.740E-16 5.789E-13 1.216E-11 2.010E-17-1.000E+00 1.840E-05 3.360E-11 RED MARR 5.210E-16 4.838E-13 1.016E-11 1.680E-17-1.000E+00 1.740E-04 1.450E-06 BONE SUR 2.870E-15 2.678E-12 5.625E-11 9.300E-17-1.OOOE+00 2.170E-03 1.810E-05 THYROID 7.830E-16 6.365E-13 1.337E-11 2.210E-17-1.000E+00 1.600E-09 1.320E-11 REMAINDER 6.340E-16 5.933E-13 1.246E-1 1 2.060E-17-1.000E+00 7.820E-05 6.660E-07 EFFECTIVE 8.180E-16 7.920E-13 1.663E-11 2.750E-17-1.000E+00 1.200E-04 9.840E-07 SKIN(FGR) 1.280E-15 2.396E-12 5.032E-11 8.320E-17-1.000E+00 0.000E+00 0.000E+00 Cm-242 GONADS 7.830E-18 4.893E-14 1.013E-12 1.700E-18-1.000E+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 1.130E-18 3.022E-15 6.257E-14 1.050E-19-1.OOOE+00 1.550E-05 8.840E-12 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-17 4.231E-14 8.759E-13 1.470E-18-1.OOOE+00 4.870E-05 4.460E-07 THYROID 4.910E-18 1.261E-14 2.610E-13 4.380E-19-1.000E+00 9.410E-10 8.820E-12 REMAINDER 2.270E-18 1.079E-14 2.235E-1 3 3.750E-1 9-1.000E+00 2.450E-06 4.020E-08 EFFECTIVE 5.690E-18 2.751 E-14 5.697E-13 9.560E-19-1.000E+00 4.670E-06 3.100E-08 SKIN(FGR) 4.290E-17 2.700E-13 5,589E-12 9.380E-18-1.OOE+00 0.000E+00 0.OOOE+00 Cm-244 GONADS 6.900E-18 4.522E-14 9.492E-131.570E-18-1.000E+00 1.590E-05 1.330E-07 BREAST 1.330E-17 5.702E-14 1.197E-12 1.980E-18-1.000E+00 1.040E-09 8.820E-12 LUNGS 7,080E-19 2.592E-15 5.441E-14 9.OOOE-20-1.OOOE+00 1.930E-05 8.810E-12 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 8.101E-13 1.340E-18-1.000E+00 1.170E-03 9.770E-06 THYROID 4.190E-18 1.146E-14 2.406E-13 3.980E-19-1.000E+00 1.010E-09 8.440E-12 REMAINDER 1.810E-18 9.821E-15 2.062E-13 3.410E-19-1.OOOE+00 4.780E-05 4.150E-07 EFFECTIVE 4.910E-18 2.529E-14 5.308E-13 8.780E-19-1.000E+00 6.700E-05 5.450E-07 SKIN(FGR) 3.910E-17 2.506E-13 5.260E-12 8.700E-18-1.OOOE+00 0.000E+00 0.000E+00

ENGINEERING SERVICES CALCULATION CONTINUATION SHEET Page -D39 (Next 0D40 Project: Nine Mile Point NuclearStation Unit: 2 Disposition: __

SOriginatoDate Reviewer/Date Calculation No. [Revision J. Metcalf 5/29/2007 Appendix E H21 C-1 03 0

<ef.

Appendix D-3: Radtrad Output (.0)file, nmp2crda.2pmp"'.out (Excerpt)

Cumulative Dose Summary EAB LPZ CR Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0o.OOOOE+00 0.OOOOE+00 0 OOOOE+00 0.001 3 .3411E-06 6.1914E-07 1.6028E-06 2.9702E-07 4.3407E-07 1. 7310E-08 0.300 6 .6560E-01 1.0631E-01 3. 1931E-01 5. 1002E-02 9. 7631E-01 3. 7945E-02 0.600 2. 0506E+00 2.8362E-01 9. 8374E-01 1.3606E-01 4.4824E+00 1. 6836E-01 0.900 3. 6726E+00 4. 6189E-01 1.7619E+00 2.2158E-01 8.8745E+00 3. 2758E-01 1.200 5 .3438E+00 6.2863E-01 2.5636E+00 3 .0157E-01 1. 3406E+01 4. 8915E-01 1.500 6. 9923E+00 7. 8247E-01 3.3544E+00 3. 7537E-01 1. 7879E+01 6. 4681E-01 1.800 8. 5916E+00 9.2422E-01 4. 1216E+00 4.4338E-01 2. 2219E+01 7. 9848E-01 2.100 1. 0133E+01 1.0550E+00 4. 8611E+00 5.0614E- 01 2. 6402E+01 9.4361E-01 2.300 1. 1127E+01 1.1367E+00 5.3381E+00 5.4532E-01 2 9101E+01 1. 0367E+00 2.600 1. 2570E+01 1.2517E+00 6.0300E+00 6. 0048E-01 3. 1579E+01 1. 1219E+00 2.900 1.3954E+01 1.3584E+00 6.6942E+00 6. 5168E- 01 3 . 3675E+01 1. 1936E+00 3.200 1. 5283E+01 1.4577E+00 7. 3317E+00 6.9929E-01 3. 5687E+01 1.2620E+00 3.500 1.6559E+01 1.5501E+00 7.9436E+00 7.4364E-01 3.7618E+01 1. 3273E+00 3.800 1.7783E+01 1.6364E+00 8.5309E+00 7.8503E-01 3. 9472E+01 1.3898E+00 4.100 1.8958E+01 1. 7171E+00 9.0946E+00 8.2373E-01 4. 1251E+01 1. 4495E+00 4.400 2. 0086E+01 1.7926E+00 9.6357E+00 8. 5995E-01 4. 2959E+01 1. 5066E+00 4.700 2. 1168E+01 1.8634E+00 1. 0155E+01 8.9391E-01 4. 4598E+01 1. 5613E+00 5.000 2. 2208E+01 1.9298E+00 1. 0654E+01 9.2578E-01 4. 6172E+01 1. 6136E+00 5.300 2.3205E+01 1.9923E+00 1.1132E+01 9.5575E-01 4. 7683E+01 1. 6637E+00 5.600 2 .4163E+01 2. 0510E+00 1.1592E+01 9. 8394E-01 4 .9134E+01 1. 7116E+00 5.900 2. 5083E+01 2. 1064E+00 1.2033E+01 1. 0105E+00 5.0526E+01 1. 7575E+00 6.200 2. 5966E+01 2.1586E+00 1.2457E+01 1.0356E+00 5.1863E+01 1. 8015E+00 6.500 2. 6814E+01 2.2079E+00 1.2864E+01 1.0592E+00 5. 3147E+01 1. 8437E+00 6.800 2. 7628E+01 2.2545E+00 1..3254E+01 1. 0815E+00 5. 4380E+01 1. 8840E+00 7.100 2. 8410E+01 2.2985E+00 1.3629E+01 1.1027E+00 5. 5564E+01 1. 9227E+00 7.400 2. 9161E+01 2.3402E+00 1.3989E+01 1. 1227E+00 5. 6701E+01 1. 9598E+00 7.700 2. 9882E+01 2.3797E+00 1.4335E+01 1. 1416E+00 5. 7793E+01 1. 9954E+00 8.000 3.0575E+01 2 .4171E+00 1.4668E+01 1.1596E+00 5. 8841E+01 2. 0295E+00 8.300 3. 0575E+01 2. 4171E+00 1.4674E+01 1. 1600E+00 5. 9326E+01 2. 0452E+00 8.600 3.0575E÷01 2 .4171E+00 1.4680E+01 1.1605E+00 5. 9688E+01 2. 0570E+00 8.900 3. 0575E+01 2. 4171E+00 1.4686E+01 1. 1609E+00 6. 0037E+01 2. 0683E+00 9.200 3. 0575E+01 2. 4171E+00 1.4691E+01 1. 1613E+00 6.0371E+01 2 0791E+00 9.500 3.0575E+01 2 . 4171E+00 1.4696E+01 1.1616E+00 6. 0693E+01 2.0894E+00 9.800 3.0575E+01 2 .4171E+00 1.4702E+01 1.1620E+00 6. 1001E+01 2.0994E+00 10.100 3. 0575E+01 2 .4171E+00 1.4706E+01 1.1623E+00 6. 1298E+01 2. 1090E+00 10.400 3.0575E+01 2 .4171E+00 1.4711E+01 1. 1626E+00 6. 1583E+01 2. 1181E+00

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24.000 3.0575E+01 2.4171E+00 1.4808E+01 1.1685E+00 6.7455E+0J 2.3057E+00 96.000 3.0575E+01 2.4171E+00 1.4808E+01 1.1685E+00 6.7501E+01 2.3072E+00 720.000 3.0575E+01 2.4171E+00 1.4808E+01 1.1685E+00 6.7501E+01 2.3072E+00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.3 7.0002E-01 1.0462E+01 1.0304E+00

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1 Project: Nine Mile Point Nuclear Station Unit: -2_ Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21 C-1 03 0 Ref.

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 STARDOSE computer code (Reference E-l) 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 LIBFILE1.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 1.63%, of which 0.77% is assumed to melt, and 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 gyoup are respectively 10% and 50%. 10% of the iodine reaches the condenser and 10% of the iodine in the condenser remains airborne. Therefore, the releasefractions for the iodine group are as follows:

From the core to the condenser:

(0.0163) x 1.8 x [(10% x 99.23%) + (50% x 0.77%)] x 10% = 3.02E-04 Fraction airborne in the condenser available for release:

10% x 3.02E-04= 3.02E-05 The release fractions used in STARDOSE for Case 2 are shown in the table below:

Fraction of Total Available Release Radionuclide Release Activity That Condenser Activity (with peaking factor of Group Fraction from Reaches-the Available for 1.8 and 2 assemblies Gap to Coolant Condenser Release to Envirnmentfailed failed 2out of ofs764)

Environment 764)

Noble Gas 10% 100% 100% 3.02E-03 Iodine 10% 10% 10% 3.02E-05 Cs, Rb 12% 1% 1% 3.63E-07

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Project: Nine Mile Point Nuclear Station Unit: 2_ Disposition:

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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 EAB 1.03E+00 1.15E+00 LPZ 1.17E+00 1.24E+00 Control Room 2.3 1E+00 2.42E+00 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 3101CF.QA.03, "Design Data Base for Application of the Revised DBA Source Term to Nine Mile Point Unit 2", Revision 0.

E-4 NUREG/CR-5106 (Manual for TACT5 - Version SAIC 9/23/87), File MLWRICRP.30.

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Project.Nine Mile Point Nuclear Station Unit: 2 Disposition:

Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21C-103 0 Ref.

Attachment E-1: STARDOSE Library File for Case 2 (LIBFILEI.TXT) n-isotopes 76 n-isotope-groups 11 Kr83m 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 Kr85 NGas NONE NONE 3.93E+022.05E-09 0 4.40E-04 0 0 0 Kr87 NGas NONE NONE 1.30E+041.51E-04 0 1.52E-01 0 0 0 Kr88 NGas NONE NONE 1.83E+046.78E-05 0 5.01E-01 0 8.36E+01 0 Kr89 NGas NONE NONE 2.22E+043.63E-03 0 3.23E-01 0 0 0 Xe131m NGas NONE NONE 3.04E+026.74E-07 0 1.44E-03 0 0 0 Xe133m NGas NONE NONE 1.63E+033.67E-06 0 5.07E-03 0 0 0 Xe133 NGas 1133Pad NONE 5.27E+041.53E-06 0 5.77E-03 0 0 0 Xe135m NGas NONE NONE 1.09E+047.56E-04 0 7.55E-02 0 0 0 Xe135 NGas 1135Pad NONE 1.91E+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 1131Org OrgI NONE NONE 2.71E +04 9.98E-07 0 6.73E-02 0 3.29E+040 11320rg OrgI NONE NONE 3.92E+048.37E-05 0 4.14E-01 0 3.81E+020 11330rg Orgi NONE NONE 5.51E+049.26E-06 0 1.09E-01 0 5.85E+030 11340rg OrgI NONE NONE 6.03E+042.20E-04 0 4,81E-01 0 1.31E+020 1135Org Orgi NONE NONE 5.16E+042.91E-05 0 3.07E-01 0 1.23E+030 1131Elem Elm_ Te131m NONE 2.71E+049.98E-07 0 6.73E-02 0 3.29E+040 1132Elem ElmI Te132 NONE 3.92E+04 8.37E-05 0 4.14E-01 0 3.81E+020 1133Elem ElmI NONE NONE 5.51E+049.26E-06 0 1.09E-01 0 5.85E+030 1134Elem ElmI NONE NONE 6.03E+042.20E-04 0 4.81E-01 0 1.31E+020 1135Elem ElmI NONE NONE 5.16E+042.91E-05 0 3.07E-01 0 1.23E+030 1131Part PrtI NONE NONE 2.71E+049.98E-07 0 6.73E-02 0 3.29E+040 1132Part PrI NONE NONE 3.92E+048.37E-05 0 4.14E-01 0 3.81E+020 1133Part PrI NONE Xe133 5.51E+049.26E-06 0 1.09E-01 0 5.85E+030 1134Part PrI NONE NONE 6.03E+042.20E-04 0 4.81E-01 0 1.31E+020 1135Part PrtI 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

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Cs136 CsGrp NONE NONE 2.28E+036.12E-07 0 3.92E-01 0 7.33E+030 Cs137 CsGrp NONE Ba137m 4.35E+037.32E-10 0 1.01E-01 0 3.19E+040 Sb127 TeGrp NONE Te127 3.01E+032.08E-06 0 1.23E-01 0 6.03E+030 Sb129 TeGrp NONE Te129 8.91E+034.46E-05 0 2.64E-01 0 6.44E+020 Te127m TeGrp NONE NONE 4.05E+027.36E-08 0 5.44E-04 0 2.15E+040 Te127 TeGrp Sb127 NONE 3.OOE+032.06E-05 0 8.95E-04 0 3.18E+020 Te129m TeGrp NONE NONE 1.30E+032.39E-07 0 1.23E-02 0 2.40E+040 Te129 TeGrp Sb129 NONE 8.76E+031.66E-04 0 1.02E-02 0 7.73E+01 0 Te131m TeGrp NONE 1131Elem3.97E+036.42E-06 0 2.76E-01 0 6.50E+030 Te132 TeGrp NONE 1132Elem3.85E+042.46E-06 0 3.81E-02 0 9.44E+030 Ba137m BaGrp Cs137 NONE 4.12E+034.53E-03 0 1.07E-01 0 0.00E+000 Ba139 BaGrp NONE NONE 4.89E+041.40E-04 0 8.03E-03 0 1.72E+020 Ba140 BaGrp NONE La140 4.71E+046.30E-07 0 3.17E-02 0 3.74E+030 Mo99 NMtIs NONE Tc99m 5.13E+042.92E-06 0 2.69E-02 0 3.96E+030 Tc99m NMtls Mo99 NONE 4.49E+043.20E-05 0 2.18E-02 0 3.26E+01 0 Rul03 NMtis NONE NONE 4.29E+042.04E-07 0 8.33E-02 0 8.96E+030 Rul05 NMtls NONE Rhl05 3.01E+044.34E-05 0 1.41E-01 0 4.55E+020 Rul06 NMtIs NONE NONE 1.76E+042.18E-08 0 3.85E-02 0 4.77E+050 Rhl05 NMtls Rul05 NONE 2.84E+045.45E-06 0 1.38E-02 0 9.55E+020 Y90 LaGrp Sr90 NONE 3.24E+033.01E-06 0 7.03E-04 0 8.44E+030 Y91 LaGrp Sr91 NONE 3.18E+041.37E-07 0 9.62E-04 0 4.88E+040 Y92 LaGrp Sr92 NONE 3.40E+045.44E-05 0 4.81 E-02 0 7.81E+020 Y93 LaGrp NONE NONE 3.96E+041.91E-05 0 1.78E-02 0 2.15E+030 Zr95 LaGrp NONE Nb95 4.46E+041.25E-07 0 1.33E-01 0 2.36E+040 Zr97 LaGrp NONE NONE 4.51E+041.14E-05 0 1.64E-01 0 4.33E+030 Nb95 LaGrp Zr95 NONE 4.48E+042.28E-07 0 1.38E-01 0 5.81E+030 La140 LaGrp Ba140 NONE 5.12E+044.78E-06 0 4.33E-01 0 4.85E+030 La141 LaGrp NONE Ce141 4.45E+044.90E-05 0 8.84E-03 0 5,81E+020 La142 LaGrp NONE NONE 4.29E+041.25E-04 0 5,33E-01 0 2.53E+020 Pr143 LaGrp Ce143 NONE 3.97E+045.92E-07 0 7.77E-05 0 8.10E+030 Nd147 LaGrp NONE NONE 1.80E+047.31E-07 0 2.29E-02 0 6.85E+030 Am241 LaGrp NONE NONE 7.48E+005.08E-11 0 3.03E-03 0 4.44E+080 Cm242 LaGrp NONE NONE 1.85E+034.93E-08 0 2.11E-05 0 1.73E+070 Cm244 LaGrp NONE NONE 1.23E+021.21E-09 0 1.82E-05 0 2.48E+080

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision H. Pustulka 5/29/2007 Check of Appendix D H21 C-103 0 Ref.

Ce141 CeGrp La141 NONE 4.47E+042.47E-07 0 1,27E-02 0 0 0 8.95E+030 0 0 0 0 0 Ce143 CeGrp NONE Pr143 4.11E+045.83E-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 2.51E+030 0 0 0 0 0 Pu238 CeGrp NONE NONE 1.45E+022.50E-10 0 1.81E-05 0 0 0 2.88E+080 0 0 0 0 0 Pu239 CeGrp NONE NONE 1.34E+019.13E-13 0 1.57E-05 0 0 0 3.08E+080 0 0 0 0 0 Pu240 CeGrp NONE NONE 1.89E+013.36E-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 6.51E+030 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 3.10E+042.03E-05 0 1.82E-01 0 0 0 9.32E+030 0 0 0 0 0 Sr92 SrGrp NONE Y92 3.38E+047.10E-05 0 2.51E-01 0 0 0 6.29E+020 0 0 0 0 0 L,)

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Project:Nine Mile Point Nuclear Station. Unit: _2_ Disposition:

Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21C-103 0 Ref.

Attachment E-2: STARDOSE Main Input File for Case 2 edittime 00.001 0.51 1.23 1.523.2348 122436 end edittime participating-isotopes Kr83m Kr85m Kr85 Kr87 Kr88 Kr89 Xe131m Xe133m Xe133 Xe135m Xe135 Xe137 Xe138 1131Org 1131Elem 1131Part 1132Org 1132Elem 1132Part 1133Org 1133Elem 1133Part 1134Org 1134Elem 1134Part 1135Org 1135Elem 1135Part Rb86 Cs134 Cs136 Cs137 Sb127 Sb129 Te127m Te127 Te129m Te129 Te131m Te132 Ba137m Ba139 Ba140 Mo99 Tc99m Rul03 Rul05 Rul06 Rhl05 Y90 Y91 Y92 Y93 Zr95 Zr97 Nb95 La140 La141 La142 Pr143 Nd147 Am241 Cm242 Cm244 Ce141 Ce143 Ce144 Np239 Pu238 Pu239 Pu240 Pu241 Sr89 Sr9O Sr9l Sr92 end.participating-isotopes core thermal-power 7321 elementaliodinefrac 0.97 organicjiodinefrac 0.03 particulateiodinefrac 0.0 releasefrac tocontrolvolume SOURCE Time NGas I-Grp CsGrp TeGrp BaGrp NMtls CeGrp LaGrp SrGrp 0.001 1.756 1.693 1.987 0 0 0 0 0 0 720 0 0 0 0 0 0 0 0 0 end to-controlvolume endreleasefrac endcore controlvolume obLtype OBJCV name SOURCE air volume 7.17e6 watervolume 0 surfacearea 0 hasrecircfilter false endcontrolvolume controlvolume

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Project: Nine Mile Point Nuclear Station Unit: 2 Disposition: __

Oginator/Date Reviewer/Date Calculaton No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21C-103 0 ief.

obj-ype OBJCV name CONDENSER airvolume 97000 watervolume 0 surfacearea 0 hasrecircfilter false end-controlvolume controlvolume obj_type OBJCR name ControlRoom airvolume 202000 watervolume 0 surface_area 0 has recirc filter false breathing-rate Time (hr) Value (cms) 720 0.00035 endbreathing-rate occupancy-factor Time (hr) Value (frac) 24 1 96 0.6 720 0.4 end occupancy-jactor endcontrolvolume junction junction-type AIRJUNCTION downstreamlocation AIRSPACE 2 upstream CORE downstream SOURCE hasfilter false flow_rate Time (hr) Value (cfm) 720 1 endflowrate end-junction junction junction.type AIRJUNCTION downstreamlocation AIRSPACE upstream SOURCE downstream CONDENSER hasfilter true flow_rate Time (hr) Value (cfm) 24 14680

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Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21C-103 0 Ret.I 720 0 end-flow-rate filterefficiency Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0.9 0.9 0.9 0.99 0.99 endfilterefficiency frac_4_daughterjesusp Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 1 1 0 0 0 0 endfrac_4_daughterjesusp endjunction junction junction-type AIRJUNCTION downstreamlocation AIRSPACE upstream CONDENSER downstream environment hasfilter true flow_rate Time (hr) Value (cfm) 24 5000 720 0 end flow rate filterefficiency Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0.9 0.9 0.9 0.99 0.99 endfilterefficiency frac_4_daughter -resusp Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 1 1 0 0 0 0 end frac_4 daughter-resusl X_overQ_4_siteboundary Time (hr) Value (s/m*3) 0.3 0.0 2.3 2.96e-5 720 0.0 end X over_Q_4_siteboundary X_over_0_4_low population_zone Time (hr) Value (s/m*3) 8 1.42e-5 720 0.0 end X over Q 4 Ilow.-population-zone X_over__Q4_ctrl room Time (hr) Value (s/m*3) 0.3 4.48E-5

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1 Project. Nine Mile Point Nuclear Station Unit: _2- Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21 C-1 03 0 Ret.

2.3 8.03E-5 8 4.48E-5 24 1.68E-5 96 1.20E-5 720 8.83E-6 end_X_over_Q_4_ctrl room-end-junction junction junction-type AIRJUNCTION downstreamlocation AIRSPACE upstream environment downstream ControlRoom hasfilter true flowrate Time (hr) Value 'cm) 720 1e6 endflowrate filter_efficiency Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0 0 0 0 0 endfilter efficiency frac_4_daughter resusp Time NobleGas Elemlodine Orglodine Partlodine Solubles Insolubles 720 0 0 0 0 0 0 endfrac_4_daughterjresusp end-junction junction junction-type AIR-JUNCTION downstreamlocation AIRSPACE upstream ControlRoom downstream environiment hasfilter false flowrate Time (hr) Value (cfm) 720 le6 endflowrate X over Q 4 ctrl room Time (hr) Value (s/m*3) 720 0 end X over_ Q4 ctrl-room X over Q 4 site boundary Time (hr) Value (s/m*3) 720 0 end X overQ_4_site boundary X-overQ_4jlow-populationzone Time (hr) Value (slm*3) 720 0

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end X over Q 4jlow-population-zone endcjunction environment breathing-ratesb Time (hr) Value (cms) 8 0.00035 720 0.0 endbreathingjrate sb breathing-rate-Ipz Time (hr) Value (cms) 8 0.00035 24 0.00018 720 0.00023 endbreathing-ratejlpz endenvironment

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Project: Nine Mile Point Nuclear Station Unit: Disposition: __

Originator/Date Reviewer/Date Calculation No. Revision H.Pustulka 5/29/2007 Check of Appendix D H21C-103 0 R*ef.

Attachment E-3: STARDOSE Results for Case 2 (Excerpts) edit time 2.000000 airspace Kr83m 6. 37E+002 Kr85m 2. 08E+003 Kr85 1. 63E+002 Kr87 1. 82E+003 Kr8 8 4. 66E+003 edit time 36.000000 Control Room thyroid wbody skin CEDE Total dose: 0. OOE+000 1.80E-001 0. OOE+000 2. 24E+000 Noble gas 0. OOE+000 1.72E-001 0. OOE+000 1.28E-001 Org iodine 0. OOE+000 2 .35E-004 0. OOE+000 6.31E-002 Elem iodine 0. OOE+000 7. 61E-003 0. OOE+000 2.04E+000 Part iodine 0. OOE+000 0. OOE+000 0. OOE+000 0. OOE+000 Cesium 0. OOE+000 1. 04E-005 0. OOE+000 1. 01E-002 Tellurium 0 . OOE+000 0. OOE+000 0. OOE+000 0. OOE+000 Barium 0. OOE+000 1.44E-006 0. OOE+000 0. OOE+000 Noble metal 0. 00E+000 0. OOE+000 0. OOE+000 0. OOE+000 Lanthanides 0. OOE+000 0. OOE+000 0. OOE+000 0. OOE+000 Cerium 0. OOE+000 0. OOE+000 0 .OOE+000 0. OOE+000 Strontinum 0. OOE+000 0. OOE+000 0. OOE+000 0. OOE+000 environment thyroid wbody skin CEDE EAB dose: 0. OOE+000 7. 93E-001 0.OOE+000 3.60E-001 LPZ dose: 0 .OOE+000 7.48E-001 0. OOE+000 4.89E-001 STARDOSE 1.01 (c) 1996-2002 Polestar Applied Technology, Inc.

Thu May 24 22:24:27 2007 Total elapsed hours: 0, mins: 0, secs: 2

ATTACHMENT 1 DESIGN VERIFICATION REPORT Document being design-verified: U DCP I-'Calc E Spec E3 NER U DBD Q Other Doc#, Rev and

Title:

H21C103, Revision 0: U2 CRDA, AST Methodology Extent of Design Verification (Briefly describe):

This calculation was desiqn verified by 1)validating all input with respect to the input database and with the AST CRDA calculation for Unit 1 (as appropriate), 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 for Case 1, MicroShield 7 for the Main Steam Line Radiation Monitor Response to a reference activity concentration, and RADTRAD for Case 2) as being acceptable for the task; and 4) validating final results to make sure that they are as expected.

Method of Design Verification:

[] Design Review U Qualification Testing E[ Alternate Calculations [] Applicability of Proven Design Results of Design Verification:

21 Fully acceptable with no issues identified Q 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..

[3 Continuation Page Follows Discipline Involvement and Approvals:

Lead Design H, Pustulka 5/2917 Verifier: Z' igna Discipcine Eesign Verifiers, ifrequired:

MicroShieid . [etcalf 5/29/07 RADTRAD MsBerg RADTRtD H.Pusula \S Disctp~ne am Date

91

~ATTACHMIIENT 2. DES~N Vk'A~jIO NNECkLST 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 inthe 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#: H21C103 Lead Design Verifiers H.Pustulka Name:

Addressed with Basis of Review Answer

.Items Yeves No NA

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