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Calculation - DC00040-120 - Fuel Handling Accident -TSC
	ML14324A324
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Site:	Summer
Issue date:	07/30/2012
From:	; South Carolina Electric & Gas Co
To:	; Office of Nuclear Reactor Regulation
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	LAR-13-02396, RC-14-0179 DC00040-120, Rev. 0
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ES-0412 ATTACHMENT I PAGE 1 OF 2 REVISION 5 Subject Code SOUTH CAROLINA ELECTRIC AND GAS COMPANY 004 CALCULATION RECORD Page 1 of 79 Calculation Title Calculation Number Revision Status Fuel Handling Accident -TSC D000040-120 0

A Parent Document System Safety Class qPartial Calc. Revision ECR 50786 N/A q NN q QR SR Complete Calc. Revision Originator Discipline Organization Date XREF Number Michael Feehan AE WorleyParsons 07/30/2012 N/A CALCULATION INFORMATION Content

Description:

The calculation determines the impact of the Alternate Source Term (AST) on the new Nuclear Operations Building (NOB) VC Summer Unit 1 Technical Support Center (TSC) dose following a postulated Fuel Handling Accident (FHA). This analysis is performed in accordance with the requirements of Appendix B of the USNRC Regulatory Guide 1.183.

Affected Components/Calculations/Documents: FSAR Section 15.4.5 Piping Reconciliation Completed per QA-CAR-0089-18: qThis Revision q Previous Revision N/A Contains Preliminary Data/Assumptions:

No q Yes, Affected Pages:

Computer Program Used:

q No Yes, Validated per WorleyParsons computer program validation process (others) vendors name q Yes, Validated in accordance with SAP-1040/ES-413 (ref. 3.4 & 3.5) q Yes, Validated [ES-0412]

q Computer Program Validation Calculation VERIFICATION q Continued, Attachment Scope:

Verify input, methodology, output and assure that the calculation is in compliance with ES-412 and addresses the work scope and deliverables documented in CGGS-11-114.

Verifier: Michael M. Waselus Assigned by: Paul L. Bunker ji(&7/3d//'z-M/c^a^l^ f.22 D7^3'^ c,2 En ineerin Personnel /Date Owner' Acceptance-Review VAI 20 Verifier/Date Responsible Engineer/Date Required for all engineering work performed by contractor personnel not enrolled in the VCSNS Engineering Training Program RECORDS A I

&LkLA 10 Z-.

To Records Mgmt: II,I Ktil

/o - Z--l Approval/Date Initials/Date A

Distribution: Calc File (Original)

ES-0412 ATTACHMENT I PAGE 2 OF 2 REVISION 5 SOUTH CAROLINA ELECTRIC & GAS COMPANY REVISION

SUMMARY

Calculation Number DC00040-120 Revision Number.

Summary Description Page 2 of 79 0

Initial Revision

DO00040-120, Revision 0 Page 3 of 79 TABLE OF CONTENTS DESCRIPTION PAGE

1.0 INTRODUCTION

.................................................................................................................. 5 1.1 Purpose.................................................................................................................................... 5 1.2 Objective................................................................................................................................. 6 1.3 Acceptance Criteria................................................................................................................. 6 1.4 Approach................................................................................................................................. 6 2.0 ASSUMPTIONS..................................................................................................................... 7 3.0 COMPUTER CODES............................................................................................................. 8

4.0 REFERENCES

....................................................................................................................... 9 5.0 DESIGN INPUTS................................................................................................................. 11 6.0 METHODOLOGY............................................................................................................... 16 7.0 COMPUTATIONS............................................................................................................... 17 7.1 FHA Inside Containment...................................................................................................... 17 7.1.1 Calculation of FHA Activity Released to Environment....................................................... 17 7.1.2 RADTRAD Model - FHA Inside Containment - Design Basis Case.................................. 18 7.2 FHA Inside the Fuel Handling Building............................................................................... 20 7.2.1 Calculation of FHA Activity Released to Environment....................................................... 20 7.2.2 RADTRAD Model - FHA Outside Containment - Design Basis Case............................... 21 8.0

SUMMARY

OF RESULTS................................................................................................. 24 9.0 DISPOSITION OF RESULTS............................................................................................. 24

DO00040-120, Revision 0 Page 4 of 79 TABLE OF CONTENTS ATT. #

DESCRIPTION PAGE 1

Containment/FHB RADTRAD FHA Model.........................................................................25 2

EXCEL Spreadsheet FHA Inside/Outside Containment - Design Basis Source..................27 3

FHA RADTRAD Source Input File for Design Basis Case:

FHA Design Basis Source.NIF..............................................................................................29 4

FHA RADTRAD Release Fraction File:

FHA Release.RFT..................................................................................................................33 5

FHA In Containment Design Basis Case RADTRAD Input/Output File:

FHA CONT Design Basis Case.oO........................................................................................35 6

FHA In FHB Design Basis Case RADTRAD Input/Output File:

FHA FHB Design Basis Case.oO...........................................................................................52 7

Westinghouse Letter SEA-CRA-98-186................................................................................69 8

Memo from D. Lengel to L. Catin, "Control Room Velocity Measurement Instrument Uncertainties"........................................................................................................................72 9

RADTRAD Dose Conversion Input File - Extra Isotopes.inp..............................................75 TABLE #

DESCRIPTION PAGE I

Design Basis Core Inventory @ 72 Hours in Ci/mtU............................................................11 2

Fraction of Fission Product Inventory in Gap........................................................................12 3

Offsite Ground Level X/Qs (sec/m3) To EAB & LPZ...........................................................12 4

Ground Level X/Qs (sec/m3) to TSC.....................................................................................13 5

Offsite and TSC Breathing Rates...........................................................................................15 6

Table No. 6: FHA Dose In Rems TEDE - TSC....................................................................24

D000040-120, Revision 0 Page 5 of 79

1.0 INTRODUCTION

1.1 PURPOSE The purpose of this analysis is to calculate the radiological dose consequences of a Fuel Handling Accident (FHA), both inside the Containment and outside Containment (in the Fuel Handling Building - FHB) in the Technical Support Center (TSC) located in the new Nuclear Operations Building (NOB) for the V. C. Summer Nuclear Station (VCSNS), based on the uprated power level of 2958 MW(t) and a cycle length of 480 days. The Alternate Source Term (AST) methodology, in accordance with the requirements of Appendix A of the USNRC Regulatory Guide 1.183 is utilized in this analysis.

The postulated FHA inside containment is the dropping of a spent fuel assembly onto the core during refueling which results in damage to the fuel assemblies. For this postulated accident, a design basis or conservative case is evaluated. There are numerous administrative controls and physical limitations which are imposed to prevent a fuel handling accident from occurring during refueling operations. Nevertheless, an accident sequence has been postulated with the objective of assessing the potential risk to the public health and safety.

It is postulated that a spent fuel assembly is dropped onto the core during refueling resulting in breaching of the fuel rod cladding. As a result of the damage, a portion of the volatile fission gases are released to the water pool covering the core. Subsequently, a fraction of the water soluble gases are absorbed in the pool with the remainder being transported through the water and into the Reactor Building atmosphere through open personnel and equipment hatches. The escaped gases are assumed to be immediately available for release to the environment and dispersed into the atmosphere.

The fuel handling accident outside containment is postulated as the dropping of a spent fuel assembly into the Spent Fuel Pool which results in damage to the fuel assemblies and the release of the volatile gaseous fission products. Similar to the evaluation of the FHA inside containment, a conservative analysis is performed for this postulated accident. The conditions and parameters assumed in analyzing the effects and consequences of this accident are identical to those utilized in the FHA inside containment except that the activity released to the environment is released through the Fuel Handling Building Exhaust System. For this evaluation no treatment of the radioactive release by the HEPA and charcoal filters of the Fuel Handling Building Exhaust System is assumed. Accordingly, the activity released into the Fuel Handling Building is identical to that presented for the FHA inside containment case.

DO00040-120, Revision 0 Page 6 of 79 1.2 OBJECTIVE The objective of this analysis is to demonstrate that the VCSNS design features, following the FHA, provide sufficient margin to ensure that the post accident TSC dose satisfy the IOCFR50.67 Accident Source Term criteria (Reference 4.1), 10CFR50 Appendix A, General Design Criteria (GDC) 19 (Reference 4.2), and the guidance in USNRC Regulatory Guide (RG) 1.183 (Reference 4.3).

1.3 ACCEPTANCE CRITERIA The TSC is to provide direct management and technical support to the control room during an accident, consequently it shall have the same radiological habitability as the control room under accident conditions. TSC personnel shall be protected from radiological hazards, including direct radiation and airborne radioactivity from in-plant sources under accident conditions, to the same degree as control room personnel.

The TSC acceptance criteria for the radiological consequences of this accident are the same as the control room radiation exposures; within the IOCFR50.67 limits; specifically:

Adequate radiation protection is provided to permit access to and occupancy of the TSC under accident conditions without personnel receiving radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent (TEDE) for the duration of the accident.

1.4 APPROACH To demonstrate the margin provided by the plant's design features in complying with the regulatory guidelines and requirements, a design basis analysis for the FHA inside and outside of Containment is evaluated. The dose models used to calculate the offsite and TSC radiological consequences are based on those presented in RG 1.183. The RADTRAD computer code (Reference 4.4) is used to calculate the offsite and TSC doses. This code was developed for the NRC and is used to calculate radiation doses by simulating the movement of radioactivity through various regions of the Containment, its removal by various processes, and its leakage to the environment. The protected TSC operator doses from the inleakage of radioactive materials into the TSC envelope are calculated based upon a whole body geometry factor as described by Murphy-Campe (Reference 4.5).

The direct dose from the external radioactive cloud in the atmosphere and the direct whole body dose from the shine of radioactive material in the reactor building are not included in this calculation because the TSC envelope is located underground and the resulting doses are negligible.

D000040-120, Revision 0 Page 7 of 79 2.0 ASSUMPTIONS 2.1 This analysis is consistent with the guidance provided in USNRC Regulatory Guide 1.183 (Reference 4.3).

2.2 Acceptable assumptions regarding core inventory and the release of radionuclides from the fuel are provided in Regulatory Position 3 (Reference 4.3, Appendix B. 1).

2.3 Alkali metals (Cs & Rb) are not included in the source term, because they are not available for release - they are 100% retained in the water per Reference 4.3 (Appendix B.3).

2.4 Consistent with the VCS UFSAR Section 15.4.5 and RG 1.183, Appendix B (Reference 4.3),

the AST FHA analysis considers a FHA inside Containment and a FHA outside Containment (inside the FHB).

2.5 Isotopes considered in the AST radiological consequence analyses are restricted to the 60 isotopes addressed in RADTRAD (Reference 4.4). For conservative reasons, additional noble gas isotopes are included in this analysis - see Section 5.2.

2.6 Per Reference 4.3, Table 3, the non-LOCA fraction of fission products inventory in the gap is acceptable for use if the peak fuel burnup does not exceed 62,000 MWD/MTU and the maximum linear heat generation rate does not exceed 6.3 kw/ft. peak rod average power for burnups exceeding 54 GWD/MTU. To account for possible variation in burnup and rod power, the Table 3 non-LOCA fraction of fission products inventory in the gap is conservatively doubled based on Reference 4.16.

2.7 Retention of the noble gases in the water in the fuel pool or reactor cavity is negligible (DF =

1), per Reference 4.3, Appendix B.3.

2.8 Radioactivity that escapes from the pool is assumed to be released over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period, per Reference 4.3, Appendix B.4.1. The release period is addressed in the RADTRAD RFT File (see Attachment 4).

2.9 Mixing and/or dilution of the radioactivity released from the pool in the FHB or Containment is not considered in this calculation. This is conservative.

2.10 All activity released from the fuel gap is instantaneously released to the pool.

2.11 The maximum fuel rod pressurization is less than 1200 psig. This is based on a USNRC Safety Guide 25 (Reference 4.8) requirement. The basis document for Safety Guide 25, the "Burley Paper" (Reference 4.10), states that the decontamination factor is not particularly sensitive to the initial gas pressure. The Burley Paper statement is as follows:

"The effect of changes in release pressure should be minimal for these bubbles, since it has been reported that for very large airflow and large Reynolds number, the bubble diameter appears to remain relatively constant for nozzle diameters of 0.4 cm or greater." In addition, Westinghouse Letter SEA-CRA-98-186 (Reference 4.15) evaluated the pool scrubbing DF with an elevated fuel pin pressure of 1500 psig and determined that the DF was acceptable at a fuel rod pressurization of 1500 psig.

D000040-120, Revision 0 Page 8 of 79 WorleyParsons performed a hand calculation, based on VCS fuel design and operating water depth, which showed a pressure of <_1500 prig is acceptable to maintain an overall effective iodine pool DF of 200. See section 5.8.

2.12 Consistent with RG 1.183 Appendix B.4.3 (Reference 4.3), the radioactive material released from the fuel pool should be assumed to be drawn into the ESF filtration system without mixing or dilution in the FHB. Per Reference VCS FSAR, for the FHA in the FHB, the safety related air handling system shall be assumed to be in operation at the time of fuel transfer, and all releases should go through the filtration and charcoal absorber system of the Fuel Handling Building Exhaust System. However for this analysis, iodine removal by filtration/charcoal for the FHA in the FHB is conservatively not credited.

2.13 Consistent with RG 1. 183 Appendices B.5.4 and B.5.5 (Reference 4.3), the reduction of radioactive material released from the Containment by ESF filtration systems may be taken into account, provided that delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system are evaluated.

Additionally, credit for dilution or mixing of the activity released from the reactor cavity by natural or forced convection inside the Containment may also be considered. For this,

evaluation, for the FHA inside and outside Containment, no credit is taken for ESF filter operation, dilution, or mixing in the Reactor Building or Fuel Handling Building.

2.14 Since RG 1. 183 (Reference 4.3) does not postulate a Loss-of Offsite-Power for the FHA event, any activity release during the event may be postulated to be released as ground level via the normal HVAC, i.e., the Containment or FHB exhaust vent or stack. Following the postulated accident inside Containment, the activity released to the atmosphere is assumed to be available for immediate release to the environment through the Reactor Building Purge System based on a discussion in FSAR 15.4.5. For conservative reasons, the FHA release for the event that occurs inside Containment is assumed to occur as ground level releases from the southwest corner of the Intermediate Building (nearest point). This analysis assumes that containment is open during fuel handling operations (i.e., personnel air lock and/or equipment hatch is open). The FHB airborne releases are also from the southwest corner of the Intermediate Building (nearest point).

2.15 Manual operator action is required for the TSC to function in the emergency mode. It is conservatively assumed the TSC personnel do not take any manual actions to isolate the TSC envelope and enter the emergency mode of operation.

2.16 As noted in the text.

3.0 COMPUTER CODES 3.1 RADTRAD version 3.03

D000040-120, Revision 0 Page 9 of 79

4.0 REFERENCES

4.1 Title 10, Code of Federal Regulations Part 50.67, "Accident Source Term."

4.2 Title 10 Code of Federal Regulations Part 50 Appendix A, "General Design Criteria for Nuclear Power Plants", Criterion 19.

4.3 USNRC Regulatory Guide 1.183, July 2000, "Alternate Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors."

4.4 NUREG/CR-6604, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", December 1997 and NUREG/CR-6604 (SAND98-0272/1),

Supplements 1 & 2, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", June 8, 1999 & October 2002.

4.5 "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Design Criteria GDC 19", K. G. Murphy and K. M. Campe, USAEC, 13th AEC Air Cleaning Conference, August 1974.

4.6 VCSNS Calculation D000040-111, Revision 0, "Short Term Accident X/Qs."

4.7 VCSNS Calculation D000040-079, Revision 3, "Atmospheric Dispersion Coefficients for Control Room."

4.8 USNRC Safety Guide 25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors", 3/23/72.

4.9 USNRC Regulatory Guide 1.49, "Power Levels of Nuclear Power Plants", Revision 1.

4.10 G. Burley, "Evaluation of Fission Product Release and Transport for a Fuel Handling Accident", Staff Technical Paper, October 5, 1971 (NRC Accession Number 8402080322 in ADAMS or PARS).

4.11 Memo from D. Lengel to L. Cartin, "Control Room Velocity Measurement Instrument Uncertainties" (Attachment 8).

4.12 VCSNS Calculation D000040-085, Revision 2, "SFP Rerack Radiological Analysis."

4.13 SAS2H-ORIGIN-S/ARP, in "Scale 4.3 - Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation", NUREG-CR-0200, Revision 5, September 1995.

4.14 Westinghouse Radiation Analysis Manual, Revision 1 for VCSNS Uprating updated 12/98 (attachment to letter CGE-98-036).

4.15 Westinghouse letter SEA-CRA-98-186, "Impact of Increased Fuel Rod Pressure on Pool Scrubbing DF for Fuel Handling Accident", July 2, 1998. (Attachment 7).

DO00040-120, Revision 0 Page 10 of 79 4.16 Byron Station, Unit Nos. I and 2, and Braidwood Station, Unit Nos. 1 and 2 - Issuance of Amendments RE: Alternate Source Term (TAC nos. MC6221, MC6222, MC6223, and MC6224), issued September 8, 2006.

4.17 "External Exposure to Radionuclides in Air, Water, and Soil - Exposure to Dose Coefficients for General Application Based on the 1987 Federal Radiation Protection Guidelines", Federal Guidance Report No. 12, Keith F. Eckerman and Jeffery C. Ryman, 1993.

4.18 "Radioactive Decay Data Tables - A Handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessments", David C. Kocher, 1981.

4.19 GMK Associates, Inc. drawings for VC Summer Nuclear Operations Building.

a.

I MS-82-202 (A2.0) - "Basement Floor Plan", RO b.

I MS-82-213 (A4.0) - "Building Sections", RO c.

I MS-82-700 (M2.0) - "Basement Plan HVAC Ductwork", RO d.

IMS-82-717 (M7.2) - "HVAC Schedules", RO 4.20 VC Summer Nuclear Operations Building, A/E Project #07023.05, "Project Manual Including Specifications Issued for Construction", GMK Associates, Inc., May 6, 2011.

4.21 VC Summer Calculation DO00040-102, Revision 1, "Fuel Handling Accidents - AST".

DO00040-120, Revision 0 Page 11 of 79 5.0 DESIGN INPUTS 5.1 Consistent with References 4.2, 4.3, and 4.9, the AST FHA dose analysis is performed at 102% of the core thermal power level (1.02 x the Licensed Thermal Power of 2900 MW(t) before Appendix K Power Uprate), or 2958 MWth (Reference 4.14).

5.2 Core inventory @2958 MWth (Reference 4.12, page 209), at time = 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months was determined by using a number of ORIGIN-S/ARP (Reference 4.13) calculations, restricted to the 60 isotopes addressed in RADTRAD (Reference 4.4). Per Assumption 2.5, for conservative reasons, additional noble gas isotopes are included in this analysis. The source inventory was obtained by running the computer code ORIGEN-S/ARP. Results are provided in Table 1.

The maximum isotopic activity for all fuel exposures is conservatively utilized in the analysis.

Table No. 1: Design Basis Core Inventory (, 72 Hours in Ci/mtU Fuel Exposure - Mwd/mtU Nuclide 35,000 40,000 45,000 50,000 70,000 maximum 1-131 9.44E+05 9.49E+05 9.53E+05 9.54E+05 9.61E+05 9.61E+05 1-132 9.32E+05 9.38E+05 9.39E+05 9.38E+05-9.33E+05 9.39E+05 1-133 2.31E+05 2.31E+05 2.30E+05 2.30E+05 2.24E+05 2.31E+05 1-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 1.18E+03 1.19E+03 1.18E+03 1.18E+03 1.16E+03 1.19E+03 Kr-85 1.06E+04 1.17E+04 1.28E+04 1.38E+04 1.70E+04 1.70E+04 Kr-85m 4.65E+00 4.47E+00 4.25E+00 4.07E+00 3.37E+00 4.65E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 2.05E-02 1.96E-02 1.86E-02 1.77E-02 1.43E-02 2.05E-02 Xe-131m 1.51E+04 1.56E+04 1.60E+04 1.64E+04 1.78E+04 1.78E+04 Xe-133 1.97E+06 1.90E+06 1.91E+06 1.89E+06 1.92E+06 1.97E+06 Xe-133m 4.41E+04 4.29E+04 4.43E+04 4.28E+04 4.40E+04 4.43E+04 Xe-135 2.57E+04 2.57E+04 2.55E+04 2.54E+04 2.46E+04 2.57E+04 Xe-135m 1.93E+02 1.94E+02 1.93E+02 1.93E+02 1.90E+02 1.94E+02 5.3 The total number of fuel rods damaged during a postulated FHA inside Containment and inside the FHB is 314 effective full-length fuel rods (Reference 4.14).

5.4 There are a total of 157 fuel assemblies in the core, with 264 fuel rods per assembly (Reference 4.14).

5.5 The maximum radial peaking factor, which is also referred to as the peak integral pin power channel factor or nuclear enthalpy rise hot channel factor, for the core is 1.7, Reference 4.14.

D000040-120, Revision 0 Page 12 of 79 5.6 The core inventory release fractions, per radionuclide group, for the gap release are per Table 3 of Reference 4.3 and provided below in Table No. 2. Per Section 2.6, the release fractions are conservatively doubled.

Table No. 2: Fraction of Fission Product Inventory in Gap Group Fraction Corrected Fraction 1-131 0.08 0.16 Kr-85 0.10 0.20 Other Noble Gases 0.05 0.10 Other Halogens 0.05 0.10 Alkali Metals (see Section 2.3) 0.12 0.24 5.7 Per Reference 4.3, Appendix B.1.3, the chemical form of radioiodine released from the fuel is 95% aerosol (CsI), 4.85% elemental and 0.15% organic. Due to the low pH of the water, Csl instantaneously disassociates and the iodine re-evolves as elemental, resulting in 99.85%

elemental (4.85% + 95%) and 0.15% organic iodine within the water.

5.8 The minimum fuel depth over the reactor core when handling fuel and over the spent fuel in the FHB is 23 feet per FSAR Section 15.4.5.

Therefore, consistent with RG 1.183, Appendix B.2, the overall effective iodine decontamination factor is 200, for the reactor core pool, with a resulting chemical species released from the water of 57% elemental and 43% organic iodine.

. 5.9 Per FSAR Section 15.4.5, the earliest time at which fuel i^ handled is 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months after shutdown. For the design basis analysis, the FHA is conservatively assumed to occur 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reactor shutdown.

5.10 Reference 4.6 provides post-accident offsite X/Q's (sec/m3) at the EAB and LPZ. These values were utilized in other calculations to determine the offsite doses as a result of FSAR Chapter 15 design basis accidents. These X/Q's are included in the RADTRAD files as a "check" for model correctness. Results are summarized in Table 3 below.

Table No. 3: Offsite Ground Level X/O's (sec/m3)

To EAB & LPZ Inside Containment Inside FHB Time Period EAB LPZ EAB LPZ 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.24E-04 5.06E-05 1.24E-04 5.06E-05

DO00040-120, Revision 0 Page 13 of 79 5.11 Reference 4.7, Appendix 2 provides the post-accident X/Q's at the TSC. TSC atmospheric dispersion factors are not adjusted to reflect the anticipated post-accident occupancy factors of Reference 4.3. Results are summarized in Table 4 below.

Per Section 2.14, the release from inside Containment and the FHB is a release via the southwest corner of the Intermediate Building (closest point to the TSC). For conservative reasons, no filtration or radionuclide removal is assumed for the Containment or FHB release.

Both releases are taken as ground level releases. In lieu of defining the model parameters required per R.G. 1.183 Appendix B Section 5 (delays in radiation detection, ESF actuation, and diversion of ventilation flow), a simplified release model from the Containment and FHB is considered. As a further explanation, the VCS stack height did not qualify for the NRC Safety Guide 25 (Reference 4.8), Item C.l.k-(footnotes 5 and 6) requirement - stack must be equal to 2.5 times the height of nearby structures to use elevated release values.

Table No. 4: Ground Level X/O's (sec/m3) to TSC(')

Time Period Inside Containment Inside FHB 0 - 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.9E-05 3.9E-05 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.3E-05 3.3E-05 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.6E-05 1.6E-05 1-4 days 1.2E-05 1.2E-05 4 - 30 days 8.7E-06 8.7E-06 Notes:

(1)

These values have not been corrected for TSC occupancy.

5.12 The VCSNS TSC design features include post accident isolation with filtered supply and pressurization. The following parameters are utilized in accessing the post-accident dose consequences to TSC personnel.

The total free volume of the TSC envelope located in the basement of the new Nuclear Operations Building (elevation 100') is 207,000 ft3 per Reference 4.19. The TSC envelope consists of all the areas depicted on the basement floor plan (Reference 4.19.a) excluding the south stairwell and area way open to above (southwest corner). The area between column lines B and G.2 and 2 and the fire wall running north-south is approximately 80' by 110' or 8,800 ft2. The area between column lines B and V and the fire wall runnin north-south and 5 is approximately 36' by (200' - 12') or 6,768 ft2. The total area is 8,800 ft + 6,768 ft2 or 15,568 ft2.

The height of the TSC envelope is determined per Reference 4.19.b, Cross Section 3. The basement and first floor finished elevations of 100' and 120' are used. A first floor thickness of 1' is assumed. The total height is (120' - 1') - 100' or 19'. The total volume of the TSC envelope is 15,568 ft2

19' or 295,792 ft3. It is assumed that 30 percent of the volume consists of components and/or structures, thus the total available free air volume is:

DC00040-120, Revision 0 Page 14 of 79 VTSC Envelope = 295,792 ft3

0.7 or 2.07E+05 ft3 For this analysis, it is conservatively assumed that the TSC never enters the emergency mode of operation (no filtration of make-up air through through the filtered air handling unit FFU-1).

TSC Normal Air Handling System flow rates, flow path and potential unfiltered leakage are determined below.

The Basement plan HVAC ductwork is provided in Reference 4.19.c. During normal operation, supply air enters the TSC envelope through the fan filter unit (FFU-1). The filters are by-passed and the make-up air is distributed throughout the TSC envelope with air handling unit AHU-0-1. Per Reference 4.19.d, AHU-0-1 has a capacity of 12,000 cfm.

Per Reference 4.20, Section 15940 - HVAC sequence of operation is as follows:

3.09 Technical Support Center (TSC)

A.

Non-Emergency Mode of Operation.

1.

AHU-0-1 shall operate as specified for VAV air handling unit(s) with static pressure optimization.

2.

Modulate return air damper in TSC space to maintain 1/8" wg positive pressure between the TSC space and the adjacent corridor.

Flow Rates under TSC Normal Operation Makeup air through AHU-0-1: 12,000 cfm A total of 13,000 cfm of unfiltered outside air is assumed to flow into and out of the TSC.

The 13,000 cfm conservatively bounds the expected design flow rate (AHU-0-1) of 12,000 cfm. The doses are conservatively calculated assuming no credit for filtration for the duration of the accident..

DC00040-120, Revision 0 Page 15 of 79 5.13 Offsite and TSC breathing rates are given in Table No. 5 per Reference 4.3, Sections 4.1.3, and 4.2.6.

Table No. 5: Offsite and TSC Breathing Rates Offsite (EAB and LPZ)

TSC Time Rate (m /sec)

Reference 4.3, Item 4.1.3 Time Rate (m /sec)

Reference 4.3, Item 4.2.6 0-8 hr 3.5E-04 0-30 days 3.5E-04 8-24 hr 1.8E-04 1-30 days 2.3E-04 5.14 Consistent with RG 1.183, Section 4.2.6 (Reference 4.3), TSC Occupancy Factors are as follows:

Occupancy Time Factor 0-24 hours 1.0 1-4 days 0.6 4-30 days 0.4 5.15 The Dose Conversion Factors (DCFs) utilized in the AST FHA analysis are from Reference 4.4, Table 1.4.3.3-2. User defined inputs for isotopes Xe-131m, Xe-133m, and Xe-135m are discussed in Section 5.18.

5.16 Dose acceptance criterion for the FHA is given as 5 Rem TEDE for the TSC (Reference 4.3, Section 4.4 and Reference 4.1).

5.17 Per Reference 4.12, page 38, there are 0.49 mtU per fuel assembly.

5.18 The dose coefficients for air submersion for Xe-131m, Xe-133m, and Xe-135m are taken from Reference 4.17. The data is input into the RADTRAD input dose conversion file: Extra Isotopes.inp 5.19 Per Reference 4.18, the required half-lives and decay schemes for the FHA design basis source term NIF files are provided below and included in Attachment 3.

Xe-131m 11.84 days 1.022976E+06 seconds Decays to stable Xe-131 (100%)

Xe-133m 2.19 days 1.892160E+05 seconds Decays to Xe-133 (100%)

Xe-133 decays to stable Cs-133 (100%)

Xe-135m 15.36 min 9.216000e+02 seconds Decays to Xe-135 (100%)

Xe-135 decays to Cs-135 (100%)

Cs-135 decays to stable Ba-135 (100%)

DC00040-120, Revision 0 Page 16 of 79 6.0 METHODOLOGY Consistent with the current licensing basis, as discussed in the VCS UFSAR and RG 1.183, Appendix B (Reference 4.3), this analysis considers two scenarios, i.e., a fuel assembly drop (1) over the reactor core and (2) over the spent fuel pool of the FHB.

The postulated fuel handling accident inside containment is the dropping of a spent fuel assembly onto the core during refueling which results in damage to the fuel assemblies. The design basis case analysis is based on Regulatory Guide 1.183 requirements.

For the FHA inside Containment, it is postulated that a spent fuel assembly is dropped onto the core during refueling resulting in breaching of the fuel rod cladding. As a result of the damage, a portion of the volatile fission gases are released to the water pool covering the core. Subsequently, a fraction of the water soluble gases are absorbed in the pool with the remainder being transported through the water and into the Reactor Building atmosphere. The escaped gases are assumed to be immediately available for release over a two hour period to the environment via the Intermediate Building nearest point and dispersed into the atmosphere. No credit is taken for a reduction in the amount of activity released due to filtration or radioactive decay due to holdup in the containment.

For the FHA in the FHB, the conditions and parameters assumed in analyzing the effects and consequences of this accident are identical to those utilized in the FHA inside containment.

Accordingly, the activity released into the Fuel Handling Building is identical to that presented for the FHA inside containment.

Utilizing the assumptions in Section 2.0 and the design input data presented in Section 5.0, the available releases from the Containment and FHB following a FHA, is calculated in compliance with RG 1.183 (Reference 4.3). This evaluation is provided in Sections 7.1 and 7.2, respectively.

For this analysis, manual operator action is required for the TSC to function in the emergency mode of operation. It is conservatively assumed that the TSC never enters the emergency mode of operation (no filtration of make-up air through through the filtered air handling unit FFU-1).

The applicable design inputs, as previously presented, are used to model the two accident FHA accident cases utilizing the RADTRAD computer code (Reference 4.4). The detailed description of the RADTRAD input can be found in Sections 7.1 and 7.2. EXCEL Spreadsheet (Attachment 2) is utilized to calculate the initial activity released to the Containment and FHB for the design basis accident.

DC00040-120, Revision 0 Page 17, of 79 7.0 COMPUTATIONS 7.1 FHA Inside Containment 7.1.1 Calculation of FHA Activity Released to Environment Airborne activity released to the environment for a FHA is calculated as follows:

A;= Ac *mtU*FD *FI*FG*DF where:

Ai

=

total activity of isotope i which is available at time T = 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months -

design basis to become airborne and be released to the environment (Ci released)

AC

=

curies of isotope i per mtU, including the uncertainty factor of 1.02 (Ci mtU), per Section 5.2 mtU

=

0.49 mtU per fuel assembly, per Section 5.17 FD

=

FRP FG fraction of assemblies damaged (unit less) 314 fuel rods damaged per Section 5.3 264 fuel rods per assembly per Section 5.4 314/264=1.19 maximum radial peaking factor assumed for damaged fuel assembly as per Section 5.5 (unit less).

1.7 fraction of isotope activity in damaged fuel rods that escapes as a gap release per Section 5.6 (unit less).

DF

=

decontamination factor within pool water for isotope i (unit less).

1 for noble gases (Section 2.7) 200 design basis for iodines (Section 5.8)

Using this methodology, the design basis isotopic activity released to the environment for the FHA is evaluated in Attachment 2 utilizing an EXCEL spreadsheet. This activity is then input to the RADTRAD computer code (Reference 4.4) via the FHA Design Basis Source.NIF file (Attachment 3) for assessment of operator dose in the TSC as described in Section 7.1.2.

D000040-120, Revision 0 Page 18 of 79 7.1.2 RADTRAD Model - FHA Inside Containment - Design Basis Case A visual representation of the RADTRAD model is given in Attachment No. 1 and is developed below (per Section 5.0, unless otherwise noted):

The activity released to the environment calculated in the previous Section and Attachment 2 are assumed to be released as a ground release from the Intermediate Building nearest point in a time period not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (Section 2.8). This is accomplished by purging the Containment free air volume (arbitrarily set to 1.0E+04 ft3) at a very high rate (1.OE+10 cfm) while releasing the available activity over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period. All leakage is immediately released to the environment from the Containment without holdup, plateout, or dilution. No isolation of the TSC is assumed for the duration of the accident.

The RADTRAD model input for the FHA case described above consists of 3 volumes, 4 flow pathways, and 3 dose locations.

Nuclide inventories (activity available for release to the environment from Attachment 2) are input as a user defined NIF files FHA Design Basis Source.NIF (Attachment 3).

Release fractions and timing data for the FHA case are input as a user defined RFT file (FHA Release.RFT - Attachment 4) for the noble gases and iodines.

7.1.2.1 RADTRAD Volume 1 represents the Containment:

Containment volume is modeled as 1.0E+04 cu ft (arbitrary-methodology is independent of volume) 100% of the AST FHA source term exiting the pool is released to the Environment 7.1.2.2 RADTRAD Volume 2 represents the Environment:

No inputs 7.1.2.3 RADTRAD Volume 3 represents the TSC:

TSC habitability volume equals 2.07E+05 ft3 7.1.2.4 RADTRAD PathwaI presents the Containment leakage term (total release within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months :

Containment air leakage rate modeled as 1.0E+10 cfm (to allow for complete release over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period) 0% efficient filters for elemental and organic species

D000040-120, Revision 0 Page 19 of 79 7.1.2.5 RADTRAD Pathway 2 represents the TSC Outside Air Intake Pathway_ (Section 5.12)

Normal Mode - Outside air intake equals 12,000 cfm No Emergency Mode or Filtration 7.1.2.6 RADTRAD Pathway 3 represents the TSC Unfiltered Air Inleakage Pathway: (Section 5.12)

TSC unfiltered air inleakage is conservatively assumed to be 1,000 cfm for the duration of the 30-day transient No filter is applied to this pathway 7.1.2.7 RADTRAD Pathway 4 represents the TSC Exhaust Air Pathway: (Section 5.12)

Normal Mode - Exhaust air flow equals intake and inleakage, 12,000 cfm plus 1,000 cfm = 13,000 cfm No filter is applied to this pathway 7.1.2.8 RADTRAD Dose Location 1 - EAB:

0-2 hour X/Q value per Table No. 3 Use breathing rate values per Table No. 5 7.1.2.9 RADTRAD Dose Location 2 - LPZ:

X/Q values per Table No. 3. _

Use breathing rate values per Table 5 7.1.2.10 RADTRAD Dose Location 3-Protected TSC:

X/Q values per Table No. 4 Use breathing rate and occupancy values per Sections 5.13 and 5.14 & Table No. 5 7.1.2.12 RADTRAD Source Term:

User Inventory file FHA Design Basis Source.NIF. This file is developed utilizing the released activity as described in Section 7.1.1 (nuclide shutdown inventory which is available at time T=72 hours to become airborne and be released to the environment).

Modeled power level as 1.003781 MWth, to obtain total 1-131 activity released at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Model isotopic decay and daughter in-growth Use the user defined RADTRAD release fraction file, FHA Release.RFT. This file defines a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release duration with a 100% release fraction in that 2-hour period The specified iodine species fractions are 0.57 elemental and 0.43 organic (Section 5.8)

Use dose conversion factors input file, Extra Isotopes.inp No additional inputs 7.1.2.13 RADTRAD Control Options:

Applicable Control Options are selected for the additional data supplied in the output printout The resulting RADTRAD output files are FHA CONT Design Basis Case.oO (Attachment 5).

D000040-120, Revision 0 Page 20 of 79 7.2 FHA Inside the Fuel Handling Building 7.2.1 Calculation of FHA Activity Released to Environment Airborne activity released to the environment for a FHA is calculated as follows:

Ai = Ac

mtU

FD

FRP *FG *DF where:

Ai

=

total activity of isotope i which is available at time T = 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months -

design basis to become airborne and be released to the environment (Ci released)

AC

=

curies of isotope i per mtU, including the uncertainty factor of 1.02 (Ci mtU), per Section 5.2 mtU

=

0.49 mtU per fuel assembly, per Section 5.17 FD

=

fraction of assemblies damaged (unit less) 314 fuel rods damaged per Section 5.3 264 fuel rods per assembly per Section 5.4 314/264=1.19 FRP

=

maximum radial peaking factor assumed for damaged fuel assembly as per Section 5.5 (unit less).

1.7 FG fraction of isotope activity in damaged fuel rods that escapes as a gap release per Section 5.6 (unit less).

DF

=

decontamination factor within pool water for isotope i (unit less).

I for noble gases (Section 2.7) 200 design basis for iodines (Section 5.8)

Using this methodology, the design basis activity released to the environment for the FHA is evaluated in Attachment 2 utilizing an EXCEL spreadsheet. This activity is then input to the RADTRAD computer code (Reference 4.4) via the FHA Design Basis Source.NIF file (Attachment 3) for assessment of the operator dose in the TSC as described in Section 7.2.2.

DO00040-120, Revision 0 Page 21 of 79 7.2.2 RADTRAD Model - FHA Outside Containment - Design Basis Case A visual representation of the RADTRAD model is given in Attachment No. 1 and is developed below (per Section 5.0, unless otherwise noted):

The activity released to the environment calculated in the previous Section and Attachment 2 is assumed to be released as a ground release from the Intermediate Building nearest point in a time period not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (Section 2.8). This is accomplished by purging the Fuel Handling Building free air volume (arbitrarily set to 1.0E+04 ft3) at a very high rate (1.OE+10 cfm) while releasing the available activity over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period. All leakage is immediately released to the environment from the Fuel Handling Building without holdup, plateout, or dilution. No isolation of the TSC is assumed for the duration of the accident.

The RADTRAD model input for the FHA case described above consists of 3 volumes, 4 flow pathways, and 3 dose locations.

Nuclide inventories (activity available for release to the environment from Attachment 2 is input as a user defined NIF files FHA Design Basis Source.NIF (Attachment 3).

Release fractions and timing data for the FHA case are input as a user defined RFT file (FHA Release.RFT - Attachment 4) for the noble gases and iodines.

7.2.2.1 RADTRAD Volume 1 represents the Containment:

Containment volume is modeled as 1.0E+04 cu ft (arbitrary-methodology is independent of volume) 100% of the AST FHA source term exiting the pool is released to the Environment 7.2.2.2 RADTRAD Volume 2 represents the Environment:

No inputs 7.2.2.3 RADTRAD Volume 3 represents the TSC:

TSC habitability volume equals 2.07E+05 ft3 Recirculating filters not utilized 7.2.2.4 RADTRAD Pathway 1 represents the Containment leakage term (total release within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months :

Containment air leakage rate modeled as 1.0E+10 cfm (to allow for complete release over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period) 0% efficient filters for elemental and organic species

DO00040-120, Revision 0 Page 22 of 79 7.2.2.5 RADTRAD Pathway 2 represents the TSC Outside Air Intake Pathway: (Section 5.12)

Normal Mode - Outside air intake equals 12,000 cfm No Emergency Mode or Filtration 7.2.2.6 RADTRAD Pathway 3 represents the TSC Unfiltered Air Inleakage Pathway: (Section 5.12)

TSC unfiltered air inleakage is conservatively assumed to be 1,000 cfm for the duration of the 30-day transient No filter is applied to this pathway 7.2.2.7 RADTRAD Pathway 4 represents the TSC Exhaust Air Pathway: (Section 5.12)

Normal Mode - Exhaust air flow equals intake and inleakage, 12,000 cfm plus 1,000 cfm = 13,000 cfm No filter is applied to this pathway 7.2.2.10 RADTRAD Dose Location 3-Protected TSC:

X/Q values per Table No. 4 Use breathing rate and occupancy values per Sections 5.13 and 5.14 & Table No. 5 7.2.2.8 RADTRAD Dose Location 1 - EAB:

0-2 hour X/Q value per Table No. 3 Use breathing rate values per Table No. 5 7.2.2.9 RADTRAD Dose Location 2 - LPZ:

X/Q values per Table No. 3.

Use breathing rate values per Table 5

D000040-120, Revision 0 Page 23 of 79 7.2.2.12 RADTRAD Source Term:

User Inventory file FHA Design Basis Source.NIF. This file is developed utilizing the released activity as described in Section 7.1.1 (nuclide shutdown inventory which is available at time T=72 hours to become airborne and be released to the environment).

Modeled power level as 1.003781 MWth, to obtain total I-131 activity released at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Model isotopic decay and daughter in-growth Use the user defined RADTRAD release fraction file, FHA Release.RFT. This file defines a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months release duration with a 100% release fraction in that 2-hour period The specified iodine species fractions are 0.57 elemental and 0.43 organic (Section 5.8)

Use dose conversion factors input file, Extra Isotopes.inp No additional inputs 7.2.2.13 RADTRAD Control Options:

Applicable Control Options are selected for the additional data supplied in the output printout The resulting RADTRAD output files are FHA FHB Design Basis Case.oO (Attachment 6).

DC00040-120, Revision 0 Page 24 of 79 8.0

SUMMARY

OF RESULTS Table No. 6 summarizes the results of the two accident scenarios, inside Containment and the FHB. As a result of the FHA, operation of the TSC HVAC system in the normal mode (no filtration) will not exceed regulatory dose requirements. As expected, the dose rate for the two accident scenarios is the same. In the original analysis, the two scenarios had different release points and consequently different X/Qs. For the TSC, one conservative X/Q was used for both accidents.

Table No. 6: FHA Dose In Rems TEDE - TSC Case Inte grated Dose Rem - TEDE Attachment EAB LPZ TSC NRC Acceptance Criteria 6.3 6.3 5.0 Inside Containment 1.3 0.53 0.36 5

Inside FHB 1.3 0.53 0.36 6

Per Section 5.16, the dose acceptance criteria (References 4.3 & 4.1) for the FHA are given as 5 Rem TEDE for the TSC. Based on the results of Table No. 6, the TSC doses resulting from the FHA are acceptable.

The EAB and LPZ doses are the same as those provided in the AST FHA calculation DC00040-102, Revision 1 (Reference 4.22).

9.0 DISPOSITION OF RESULTS The results of this calculation are incorporated into the VCSNS FSAR 15.4.5.

DO00040-120, Revision 0 Page 25 of 79 Containment/FHB RADTRAD FHA Model

DO00040-120, Revision 0 Page 26 of 79 Volume 1 Gap Release Volume 1.0+04 ft3 (arbitrary volume)

RADTRAD Model for Inside/Outside Containment (FHB) FHA Source Release FP 1 1.0E+10 cfm Volume 2 FP 2 - 12,000 cfm makeup (0 - 720 hr.)

no filtration Volume 3 (arbitrary flow rate)

No filtration or holdup Environment FP 3 - 1,000 cfm unfiltered inleakage (0 -720 hr.

unfiltered inleakage/ damper leakage /

ingress/egress TSC Habitability Envelope (2.07E+05 ft3)

FP 4 - TSC exhaust: makeup plus unfiltered inleakage 13,000 cfm (0 - 720 hr.)

DC00040-120, Revision 0 Page 27 of 79 EXCEL Spreadsheet FHA Inside/Outside Containment Design Basis Source

D000040-120, Revision 0 Page 28 of 79 Design Basis Source Term (T = 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) Available for Release to the Environment Isotope Section 5.2 Ci/mtU at T = 72 hrs.

mtU per Assembly Fraction of Damaged Assemblies Fuel Radial Peaking Factor Gap Fraction Released Fuel Pool Effective DF Activity Released Curies 1-131 9.61E+05 4.90E-01 1.19E+00 1.70 0.16 200 7.62E+02 1-132 9.39E+05 4.90E-01 1.19E+00 1.70 0.10 200 4.65E+02 1-133 2.31E+05 4.90E-01 1.19E+00 1.70 0.10 200 1.14E+02 1-134 0.00E+00 4.90E-01 1.19E+00 1.70 0.10 200 0.00E+00 1-135 1.19E+03 4.90E-01 1.19E+00 1.70 0.10 200 5.90E-01 4.90E-01 Kr-85 1.70E+04 4.90E-01 1.19E+00 1.70 0.20 1

3.37E+03 Kr-85m 4.65E+00 4.90E-01 1.19E+00 1.70 0.10 1

4.61 E-01 Kr-87 0.00E+00 4.90E-01 1.19E+00 1.70 0.10 1

0.00E+00 Kr-88 2.05E-02 4.90E-01 1.19E+00 1.70 0.10 1

2.03E-03 Xe-131m 1.78E+04 4.90E-01 1.19E+00 1.70 0.10 1

1.76E+03 Xe-133 1.97E+06 4.90E-01 1.19E+00 1.70 0.10 1

1.95E+05 Xe-133m 4.43E+04 4.90E-01 1.19E+00 1.70 0.10 1

4.39E+03 Xe-135 2.57E+04 4.90E-01 1.19E+00 1.70 0.10 1

2.55E+03 Xe-135m 1.94E+02 4.90E-01 1.19E+00 1.70 0.10 1

1.92E+01 Per Sections 7.1 and 7.2 Damaged Fuel Rods = 314 Full Fuel Rods per Assembly = 264 Radial Peaking Factor = 1.7 Uranium mass/assembly (mtU) = 0.49

DO00040-120, Revision 0 Page 29 of 79 FHA RADTRAD Source Input File for Design Basis Case:

FHA Design Basis Source.NIF

D000040-120, Revision 0 Page 30 of 79 Nuclide Inventory Name:

VCS FHA Design Basis Source Terms @ 72 Hours Power Level:

0. 1000E+01 Nuclides:

14 Nuclide 001:

Kr-85 1

0.3382974720E+09 0.8500E+02 3.3700E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide Kr-85m 002:

1 0.1612800000E+05 0.8500E+02 4.6100E-01 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-87 1

0.4578000000E+04 0.8700E+02 0.0000E+00 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-88 1

0.1022400000E+05 0.8800E+02 2.0300E-03 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

1-131 2

0.6946560000E+06

0. 1310E+03 7.6200E+02 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

1-132 2

0.8280000000E+04

D000040-120, Revision 0 Page 31 of 79 0.1320E+03 4.6500E+02 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

1-133 2

0.7488000000E+05 0.1330E+03 1.1400E+02 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nuclide 008:

1-134 2

0.3156000000E+04 0.1340E+03 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

1-135 2

0.2379600000E+05 0.1350E+03 5.9000E-01 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 010 Xe-131m 1

1.0229760000E+06 0.1310E+03 1.7600E+03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 011:

Xe-133 1

0.4531680000E+06 0.1330E+03 1.9500E+05 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Xe-133m 1

1.8921600000E+05 0.1330E+03

D000040-120, Revision 0 Page 32 of 79 4.3900E+03 Xe-133 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Xe-135 1

0.3272400000E+05 0.1350E+03 2.5500E+03 Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 014:

Xe-135m 1

9.2167177120E+02 0.1350E+03 1.9200E+01 Xe-135 1.0000E+00 Cs-135 1.0000E+00 none 0.0000E+00 End of Nuclear Inventory File i

DO00040-120, Revision 0 Page 33 of 79 FHA RADTRAD Release Fraction File:

FHA Release.RFT

D000040-120, Revision 0 Page 34 of 79 Release Fraction and Timing Altered for FHA PWR, NUREG-1465, Tables 3.12 & 3.13, June 1992 Duration (h):

2.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Noble Gases:

1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Iodine:

1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Cesium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Tellurium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Strontium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Barium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Ruthenium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Cerium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Lanthanum:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Non-Radioactive Aerosols (kg):

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 End of Release File

DC00040-120, Revision 0 Page 35 of 79 FHA In Containment Design Basis Case RADTRAD Input/Output File:

FHA CONT Design Basis Case.oO

DC00040-120, Revision 0 Page 36 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 11:57:13 File information Plant file

= C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA CONT Design Basis Case.psf Inventory file

= c:\\program files\\radtrad3_03\\vcs tsc\\fha\\fha design basis source.nif Release file

= c:\\program files\\radtrad3 03\\vcs tsc\\fha\\fha release.rft Dose Conversion file = c:\\program files\\radtrad3 03\\vcs tsc\\fha\\extra isotopes.inp Radtrad 3.03 4/15/2001 FHA Inside Containment - Design basis Nuclide Inventory File:

c:\\program files\\radtrad3_03\\vcs tsc\\fha\\fha design basis source.nif Plant Power Level:

1.0038E+00 Compartments:

3 Compartment 1:

Gap Release Volume 3

1.0000E+04 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

0

D000040-120, Revision 0 Page 37 of 79 0

Compartment 3:

TSC 1

2.0700E+05 0

0 0

Pathways:

4 Pathway 1:

Gap Release Volume to Environment 1

2 2

Pathway 2:

Environment to TSC - Makeup 2

3 2

Pathway 3:

Environment to TSC - Inleakage 2

3 2

Pathway 4:

TSC to Environment - Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\radtrad3 03\\vcs tsc\\fha\\extra isotopes.inp c:\\program files\\radtrad3 03\\vcs tsc\\fha\\fha release.rft 0.0000E+00 1

0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

D000040-120, Revision 0 Page 38 of 79 1

1 0

0 0

Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Pathways:

4 Pathway 1:

0 0

0 1

2 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 2:

0 0

0 1

2

D000040-120, Revision 0 Page 39 of 79 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 3:

0 0

0 1

2 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 4:

0 0

0 1

2 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 2

1 2

0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00

DC00040-920, Revision 0 Page 40 of 79 0

Location 2:

LPZ 2

1 2

0.0000E+00 5.0600E-05 2.0000E+00 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 3:

TSC 3

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 6

0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Simulation Parameters:

1 0.0000E+00 0.0000E+00 Output Filename:

C:\\Program Files\\radtrad3_03\\VCS TSC\\FHA\\FHA CONT Design Basis Case.oO 1

1 1

0 1

End of Scenario File

D000040-120, Revision 0 Page 41 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 11:57:13 Plant Description Number of Nuclides = 14 Inventory Power =

1.0000E+00 MWth Plant Power Level =

1.0038E+00 MWth Number of compartments

=

3 Compartment information Compartment number 1 (Source term fraction =

1.0000E+00 Name: Gap Release Volume Compartment volume =

1.0000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1:

Gap Release Volume to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1:

Gap Release Volume to Environment Inlet Pathway Number 4:

TSC to Environment - Exhaust Exit Pathway Number 2:

Environment to TSC - Makeup Exit Pathway Number 3: Environment to TSC - Inleakage Compartment number 3 Name: TSC Compartment volume =

2.0700E+05 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2:

Environment to TSC - Makeup Inlet Pathway Number 3: Environment to TSC - Inleakage Exit Pathway Number 4:

TSC to Environment - Exhaust Total number of pathways =

4

D000040-120, Revision 0 Page 42 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 11:57:13 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 2.000000 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 1.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00' 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.700E+00 6.316E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1

Inventory Power =

MWt Nuclide Name Group Specific Inventory (Ci/MWt) half Whole Body life DCF (s)

(Sv-m3/Bq-s)

Inhaled Thyroid (Sv/Bq)

Inhaled Effective (Sv/Bq)

Kr-85 1

3.370E+03 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-85m 1

4.610E-01 1.613E+04 7.480E-15 0.000.E+00 0.000E+00 Kr-88 1

2.030E-03 1.022E+04 1.020E-13 0.000E+00 0.000E+00 I-131 2

7.620E+02 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2

4.650E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2

1.140E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-135 2

5.900E-01 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.760E+03 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133 1

1.950E+05 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-133m 1

4.390E+03 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-135 1

2.550E+03 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-135m 1

1.920E+01 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 1-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1.00 none 0.00 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 Cs-135 1.00 none 0.00 Iodine fractions Aerosol

=

0.0000E+00

DC0004O-120, Revision 0 Page 43 of 79 Elemental

=

5.7000E-01 Organic

=

4.3000E-01 COMPARTMENT DATA Compartment number 1:

Gap Release Volume Compartment number 2:

Environment Compartment number 3:

TSC PATHWAY DATA Pathway number 1: Gap Release Volume to Environment Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Environment to TSC - Makeup Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to TSC - Inleakage Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: TSC to Environment - Exhaust Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location EAB is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 1.2400E-04

DC00040-120, Revision 0 Page 44 of 79 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m'3

sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location LPZ is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 5.0600E-05 2.0000E+00 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location TSC is in compartment 3

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr)

Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

D000040-120, Revision 0 Page 45 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 11:57:13 Dose, Detailed model and Detailed Inventory Output Detailed model information at time (H) =

2.0000 EAB Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 Accumulated dose (rem) 7.4202E-02 r.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6311E-03 9.9905E+00 3.0803E-01 Accumulated dose (rem) 2.6311E-03 9.9905E+00 3.0803E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85 2.8190E-05 7.1851E-11 5.0905E+14 7.5098E+09 Kr-85m 2.8299E-09 3.4388E-19 2.4363E+06 8.8356E+05 1-131 6.3285E-06 5.1047E-14 2.3466E+ll 1.6920E+09 1-132 2.1289E-06 2.0625E-16 9.4094E+08 7.7826E+08 1-133 8.9212E-07 7.8753E-16 3.5659E+09 2.4576E+08 1-135 4.0016E-09 1.1395E-18 5.0829E+06 1.1861E+06 Xe-131m 1.4651E-05 1.7403E-13 8.0004E+ll 3.9125E+09 Xe-133 1.6137E-03 8.6211E-12 3.9036E+13 4.3221E+ll Xe-133m 3.5767E-05 7.9785E-14 3.6126E+ll 9.6550E+09 Xe-135 1.8318E-05 7.1731E-15 3.1998E+10 5.2714E+09

DC00040-120, Revision 0 Page 46 of 79 Xe-135m 1.4235E-09 1.5700E-20 7.0036E+04 8.0096E+06 Gap Release Volume Transport Group Inventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.4928E+14 0.0000E+00 Elemental I (atoms) 1.3633E+ll 0.0000E+00 Organic I (atoms) 1.0285E+ll 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.2918E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.3463E-14 Total I (Ci) 9.3535E-06 Gap Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

2.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.6773E+23 Elemental I (atoms) 0.0000E+00 4.1985E+19 Organic I (atoms) 0.0000E+00 3.1673E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

8.0000 EAB Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4561E-09 3.0430E-07 1.0752E-08 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9107E-04 1.5395E+00 4.7416E-02 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Gap Release Volume Transport Group Inventory:

Time (h) =

8.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Decay

D000040-120, Revision 0 Page 47 of 79 Gap Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

8.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms)

O'.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

24.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

24.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.2628E-14 2.2746E-10 6.9887E-12 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay Gap Release Volume Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I

(Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Time (h) =

24.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

96.0000

DC00040-120, Revision 0 Page 48 of 79 EAB Doses:

Time (h) =

96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5240E-40 1.6355E-36 5.0186E-38 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 96.0000 Ci kg Atoms Gap Release Volume Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Decay Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I

(Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Time (h) =

96.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H)

=

720.0000 EAB Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem)-

0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01

DC00040-120, Revision 0 Page 49 of 79 TSC Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3248-158 1.2434-154 3.8091-156 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Gap Release Volume Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I

(Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Time (h) = 720.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 837

D000040-120, Revision 0 Page 50 of 79 1-131 Summary Time (hr)

Gap Release Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 6.3741E-06 2.1246E-01 5.0785E-05 0.401 6.3650E-06 1.5327E+02 1.8901E-02 0.701 6.3581E-06 2.6775E+02 2.2499E-02 1.001 6.3512E-06 3.8212E+02 2.3642E-02 1.301 6.3444E-06 4.9636E+02 2.3993E-02 1.601 6.3376E-06

6. 1047E+02 2.4088E-02 1.901 6.3307E-06 7.2447E+02 2.4102E-02 2.000 6.3285E-06 7.6202E+02 2.4099E-02 2.300 0.0000E+00 7.6202E+02 7.7730E-03 2.600 0.0000E+00 7.6202E+02 2.5071E-03 2.900 0.0000E+00 7.6202E+02 8.0867E-04 3.200 0.0000E+00 7.6202E+02 2.6083E-04 3.500 0.0000E+00 7.6202E+02 8.4130E-05 3.800 0.0000E+00 7.6202E+02 2.7136E-05 4.100 0.0000E+00 7.6202E+02 8.7525E-06 4.400 0.0000E+00 7.6202E+02 2.8231E-06 4.700 0.0000E+00 7.6202E+02

9. 1057E-07 5.000 0.0000E+00 7.6202E+02 2.9370E-07 5.300 0.0000E+00 7.6202E+02

9. 4731E-08 5.600 0.0000E+00 7.6202E+02 3.0555E-08 5.900 0.0000E+00 7.6202E+02 9.8554E-09 6.200 0.0000E+00 7.6202E+02

3. 1788E-09 6.500 0.0000E+00 7.6202E+02 1.0253E-09 6.800 0.0000E+00 7.6202E+02

3. 3071E-10 7.100 0.0000E+00 7.6202E+02

1. 0667E-10 7.400 0.0000E+00 7.6202E+02

3. 4405E-11 7.700 0.0000E+00 7.6202E+02 1.1097E-11 8.000 0.0000E+00 7.6202E+02

3. 5794E-12 8.300 0.0000E+00 7.6202E+02

1. 1545E-12 8.600 0.0000E+00 7.6202E+02 3.7238E-13 8.900 0.0000E+00 7.6202E+02 1.2011E-13 9.200 0.0000E+00 7.6202E+02

3. 8741E-14 9.500 O.0000E+00 7.6202E+02 1.2496E-14 9.800 0.0000E+00 7.6202E+02 4.0304E-15 10.100 0.0000E+00 7.6202E+02 1.3000E-15 10.400 0.0000E+00 7.6202E+02 4.1930E-16 24.000 0.0000E+00 7.6202E+02 2.2146E-38 96.000 0.0000E+00 7.6202E+02 2.5526-156 720.000 0.0000E+00 7.6202E+02 0.0000E+00

D000040-120, Revision 0 Page 51 of 79 Cumulative Dose Summary EAB LPZ TSC Time (hr)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TEDE (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.401 7.3925E+00 2.6387E-01 3.0166E+00 1.0768E-01 1.1117E+00 3.4311E-02 0.701 1.2911E+01 4.6040E-01 5.2687E+00 1.8787E-01 2.6154E+00 8.0700E-02 1.001 1.8422E+01 6.5627E-01 7.5172E+00 2.6780E-01 4.2736E+00 1.3184E-01 1.301 2.3923E+01 8.5152E-01 9.7623E+00 3.4747E-01 5.9799E+00 1.8445E-01 1.601 2.9417E+01 1.0462E+00 1.2004E+01 4.2690E-01 7.7000E+00 2.3746E-01 1.901 3.4903E+01 1.2402E+00 1.4242E+01 5.0610E-01 9.4227E+00 2.9054E-01 2.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 9.9905E+00 3.0803E-01 2.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1034E+01 3.4016E-01 2.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1370E+01 3.5052E-01 2.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1478E+01 3.5386E-01 3.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1513E+01 3.5493E-01 3.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1525E+01 3.5528E-01 3.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1528E+01 3.5539E-01 4.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1529E+01 3.5543E-01 4.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5544E-01 4.700 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.700 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 10.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 10.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 24.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 96.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 720.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)

(rem)

(rem) 0.0 1.8184E-01 3.6709E+01 1.3041E+00

D000040-120, Revision 0 Page 52 of 79 FHA In FHB Design Basis Case RADTRAD Input/Output File:

FHA FHB Design Basis Case.oO

D000040-120, Revision 0 Page 53 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 12:12:05 File information Plant file

= C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA FHB Design Basis Case.psf Inventory file

= C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA Design Basis Source.NIF Release file

= C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA Release.RFT Dose Conversion file = C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\Extra Isotopes.inp Radtrad 3.03 4/15/2001 FHA Inside FHB - Design Basis Nuclide Inventory File:

C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA Design Basis Source.NIF Plant Power Level:

1.0038E+00 Compartments:

3 Compartment 1:

Gap Release Volume 3

1.0000E+04 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

0

DC00040-120, Revision 0 Page 54 of 79 0

Compartment 3:

TSC 1

2.0700E+05 0

0 0

Pathways:

4 Pathway 1:

Gap Release Volume to Environment 1

2 2

Pathway 2:

Environment to TSC - Makeup 2

3 2

Pathway 3:

Environment to TSC - Inleakage 2

3 2

Pathway 4:

TSC to Environment - Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\Extra Isotopes.inp C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA Release.RFT 0.0000E+00 1

0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

D000040-120, Revision 0 Page 55 of 79 1

1 0

0 0

Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Pathways:

4 Pathway 1:

0 0

0 1

2 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 2:

0 0

0 1

2

D000040-120, Revision 0 Page 56 of 79 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 3:

0 0

0 1

2 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 4:

0 0

0 1

2 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 2

1 2

0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00

i D000040-120, Revision 0 Page 57 of 79 0

Location 2:

LPZ 2

1 2

0.0000E+00 2.0000E+00 1

4 0.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02

.0600E-05 0.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 0.0000E+00 0

Location 3:

TSC 3

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 6

0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Simulation Parameters:

1 0.0000E+00 0.0000E+00 Output Filename:

C:\\Program Files\\radtrad3 03\\VCS TSC\\FHA\\FHA FHB Design Basis Case.oO 1

1 1

0 1

End of'Scenario File

D000040-120, Revision 0 Page 58 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 12:12:05 Plant Description Number of Nuclides = 14 Inventory Power =

1.0000E+00 MWth Plant Power Level =

1.0038E+00 MWth Number of compartments

=

3 Compartment information Compartment number 1 (Source term fraction =

1.0000E+00 Name:, Gap Release Volume Compartment volume =

1.0000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1:

Gap Release Volume to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1:

Gap Release Volume to Environment Inlet Pathway Number 4:

TSC to Environment -

Exhaust Exit Pathway Number 2:

Environment to TSC -

Makeup Exit Pathway Number 3:

Environment to TSC -

Inleakage Compartment number 3 Name: TSC Compartment volume =

2.0700E+05 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2:

Environment to TSC -

Makeup Inlet Pathway Number 3: Environment to TSC - Inleakage Exit Pathway Number 4:

TSC to Environment - Exhaust Total number of pathways =

4

D000040-120, Revision 0 Page 59 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 12:12:05 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 2.000000 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 1.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.700E+00 0.0000E+00 0.0000E+00 6.316E-03 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 0.0000E+00 0.0000E+00 0.000E+00 Inventory Power =

1.

MWt Nuclide Name Group Specific Inventory (Ci/MWt) half life (s)

Whole Body DCF (Sv-m3/Bq-s)

Inhaled Thyroid (Sv/Bq)

Inhaled Effective (Sv/Bq)

Kr-85 1

3.370E+03 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-85m 1

4.610E-01 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-88 1

2.030E-03 1.022E+04 1.020E-13 0.000E+00 0.000E+00 1-131 2

7.620E+02 6.947E+05 1.820E-14 2.920E-07 8.890E-09 1-132 2

4.650E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 1-133 2

1.140E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-135 2

5.900E-01 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.760E+03 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133 1

1.950E+05 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-133m 1

4.390E+03 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-135 1

2.550E+03 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-135m 1

1.920E+01 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 1-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1.00 none 0.00 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 Cs-135 1.00 none 0.00 Iodine fractions Aerosol

=

0.0000E+00

DC00040-120, Revision 0 Page 60 of 79 Elemental

=

5.7000E-01 Organic

=

4.3000E-01 COMPARTMENT DATA Compartment number 1:

Gap Release Volume Compartment number 2:

Environment Compartment number 3:

TSC PATHWAY DATA Pathway number 1: Gap Release Volume to Environment Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Environment to TSC - Makeup Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to TSC - Inleakage Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: TSC to Environment - Exhaust Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location EAB is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 1.2400E-04

D000040-120, Revision 0 Page 61 of 79 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location LPZ is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 5.0600E-05 2.0000E+00 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-l) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location TSC is in compartment 3

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr)

Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA.- SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

DC00040-120, Revision 0 Page 62 of 79 RADTRAD Version 3.03 (Spring 2001) run on 11/07/2011 at 12:12:05 Dose, Detailed model and Detailed Inventory Output Detailed model information at time (H) =

2.0000 EAB Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6311E-03 9.9905E+00 3.0803E-01 Accumulated dose (rem) 2.6311E-03 9.9905E+00 3.0803E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85 2.8190E-05 7.1851E-11 5.0905E+14 7.5098E+09 Kr-85m 2.8299E-09 3.4388E-19 2.4363E+06 8.8356E+05 1-131 6.3285E-06 5.1047E-14 2.3466E+ll 1.6920E+09 1-132 2.1289E-06 2.0625E-16 9.4094E+08 7.7826E+08 1-133

.8.9212E-07 7.8753E-16 3.5659E+09 2.4576E+08 1-135 4.0016E-09 1.1395E-18 5.0829E+06 1.1861E+06 Xe-131m 1.4651E-05 1.7403E-13 8.0004E+11 3.9125E+09 Xe-133 1.6137E-03 8.6211E-12 3.9036E+13 4.3221E+ll Xe-133m 3.5767E-05 7.9785E-14 3.6126E+11 9.6550E+09 Xe-135 1.8318E-05 7.1731E-15 3.1998E+10 5.2714E+09

D000040-120, Revision 0 Page 63 of 79 Xe-135m 1.4235E-09 1.5700E-20 7.0036E+04 8.0096E+06 Gap Release Volume Transport Group Inventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.4928E+14 0.0000E+00 Elemental I (atoms) 1.3633E+ll 0.0000E+00 Organic I (atoms) 1.0285E+ll 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.2918E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.3463E-14 Total I

(Ci) 9.3535E-06 Gap Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

2.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.6773E+23 Elemental I (atoms) 0.0000E+00 4.1985E+19 Organic I (atoms) 0.0000E+00 3.1673E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

8.0000 EAB Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4561E-09 3.0430E-07 1.0752E-08 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9107E-04 1.5395E+00 4.7416E-02 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Decay Gap Release Volume Transport Group Inventory:

Time (h) =

8.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I

(Ci) 0.0000E+00

D000040-120, Revision 0 Page 64 of 79 Gap Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

8.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

24.0000 EAB Doses:

Time.(h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.2628E-14 2.2746E-10 6.9887E-12 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Gap Release Volume Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H) =

96.0000 Decay EAB Doses:

D000040-120, Revision 0 Page 65 of 79 Time (h) =

96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) =

96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

Time (h) =

96.0000 Whole Body Thyroid.

TEDE Delta dose (rem) 3.5240E-40 1.6355E-36 5.0186E-38 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 96.0000 Ci kg Atoms Gap Release Volume Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Decay Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Time (h) =

96.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 Detailed model information at time (H)

=

720.0000 EAB Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.8184E-01 3.6709E+01 1.3041E+00 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 7.4202E-02 1.4980E+01 5.3216E-01 TSC Doses:

DC0004O-120, Revision 0 Page 66 of 79 Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3248-158 1.2434-154 3.8091-156 Accumulated dose (rem) 3.0221E-03 1.1530E+01 3.5545E-01 Gap Release Volume Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Gap Release Volume Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00' Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I

(Ci) 0.0000E+00 Gap Release Volume to Environment Transport Group Inventory:

Time (h) = 720.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.6938E+23 Elemental I (atoms) 0.0000E+00 4.2394E+19 Organic I (atoms) 0.0000E+00 3.1981E+19 Aerosols (kg) 0.0000E+00 0.0000E+00 837

D000040-120, Revision 0 Page 67 of 79 1-131 Summary Time (hr)

Gap Release Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 6.3741E-06 2.1246E-01 5.0785E-05 0.401 6.3650E-06 1.5327E+02 1.8901E-02 0.701 6.3581E-06 2.6775E+02 2.2499E-02 1.001 6.3512E-06 3.8212E+02 2.3642E-02 1.301 6.3444E-06 4.9636E+02 2.3993E-02 1.601 6.3376E-06

6. 1047E+02 2.4088E-02 1.901 6.3307E-06 7.2447E+02 2.4102E-02 2.000 6.3285E-06 7.6202E+02 2.4099E-02 2.300 0.0000E+00 7.6202E+02 7.7730E-03 2.600 0.0000E+00 7.6202E+02 2.5071E-03 2.900 0.0000E+00 7.6202E+02 8.0867E-04 3.200 0.0000E+00 7.6202E+02 2.6083E-04 3.500 0.0000E+00 7.6202E+02 8.4130E-05 3.800 0.0000E+00 7.6202E+02 2.7136E-05 4.100 0.0000E+00 7.6202E+02 8.7525E-06 4.400.

0.0000E+00 7.6202E+02 2.8231E-06 4.700 0.0000E+00 7.6202E+02 9.1057E-07 5.000 0.0000E+00 7.6202E+02 2.9370E-07 5.300 0.0000E+00 7.6202E+02 9.4731E-08 5.600 0.0000E+00 7.6202E+02 3.0555E-08 5.900 0.0000E+00 7.6202E+02 9.8554E-09 6.200 0.0000E+00 7.6202E+02 3.1788E-09 6.500 0.0000E+00 7.6202E+02 1.0253E-09 6.800 0.0000E+00 7.6202E+02 3.3071E-10 7.100 0.0000E+00 7.6202E+02 1.0667E-10 7.400 0.0000E+00 7.6202E+02 3.4405E-11 7.700 0.0000E+00 7.6202E+02 1.1097E-11 8.000 0.0000E+00 7.6202E+02

3. 5794E-12 8.300 0.0000E+00 7.6202E+02 1.1545E-12 8.600 0.0000E+00 7.6202E+02

3. 7238E-13 8.900 0.0000E+00 7.6202E+02 1.2011E-13 9.200 0.0000E+00 7.6202E+02 3.8741E-14 9.500 0.0000E+00 7.6202E+02 1.2496E-14 9.800 0.0000E+00 7.6202E+02 4.0304E-15 10.100 0.0000E+00 7.6202E+02 1.3000E-15 10.400 0.0000E+00 7.6202E+02 4.1930E-16 24.000 0.0000E+00 7.6202E+02 2.2146E-38 96.000 0.0000E+00 7.6202E+02 2.5526-156 720.000 0.0000E+00 7.6202E+02 0.0000E+00

D000040-120, Revision 0 Page 68 of 79 Cumulative Dose Summary EAB LPZ TSC Time (hr)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TEDE (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.401 7.3925E+00 2.6387E-01 3.0166E+00 1.0768E-01 1.1117E+00 3.4311E-02 0.701 1.2911E+01 4.6040E-01 5.2687E+00 1.8787E-01 2.6154E+00 8.0700E-02 1.001 1.8422E+01 6.5627E-01 7.5172E+00 2.6780E-01 4.2736E+00 1.3184E-01 1.301 2.3923E+01 8.5152E-01 9.7623E+00 3.4747E-01 5.9799E+00 1.8445E-01 1.601 2.9417E+01 1.0462E+00 1.2004E+01 4.2690E-01 7.7000E+00 2.3746E-01 1.901 3.4903E+01 1.2402E+00 1.4242E+01 5.0610E-01 9.4227E+00 2.9054E-01 2.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 9.9905E+00 3.0803E-01 2.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1034E+01 3.4016E-01 2.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1370E+01 3.5052E-01 2.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1478E+01 3.5386E-01 3.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1513E+01 3.5493E-01 3.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1525E+01 3.5528E-01 3.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1528E+01 3.5539E-01 4.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1529E+01 3.5543E-01 4.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5544E-01 4.700 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 5.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 6.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 7.700 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.300 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.600 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 8.900 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.200 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.500 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 9.800 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 10.100 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 10.400 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 24.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 96.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 720.000 3.6709E+01 1.3041E+00 1.4980E+01 5.3216E-01 1.1530E+01 3.5545E-01 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)

(rem)

(rem) 0.0 1.8184E-01 3.6709E+01 1.3041E+00

DO00040-120, Revision 0 Page 69 of 79 Westinghouse Letter SEA-CRA-98-186

D000040-120, Revision 0 Page 70 of 79 794 SAE.CRA 9g-/lib Rom Containment and Radiological Analysis WIN 2$4-Sf83 Due July 2, 1998 g+tieot Impact of Increased Furr1 Rod Possum on Pool Scrubbing OF for Fuel Handling Accident K. C. Koskina sec

1. A. Gresham U. Bachrach The following is provided in rosponso to your request fns

discussion that can be seat to our castonners addressing the impact of higher fad pin Possum an 60 pool scrubbing DF trued for fact handling accident dose analysis. This discassian is derived float ealwlatin tt>%e C1t.CRA 98-063, Rev. a 911/91.

In pcrfoaming radiological oonrsequences analysis of the postulated fhelbandling accident (FBA),

credit is taste for seaoval of radioactive iodine froaa the find pin tuna they bobble up through the pool of water. A pool scrubbing DF vahee of 133 for elemental iodine is specified in Regulatory Guido 113. This DF is based on tbe3 pin posture being no greater thus 1200 psig idea a pool depth of 23 feet 'Reg. Guide 113 awes that, `For rc*Casc pressures greater than 1200 prig and water depths less than 23 feat, the iodine deeontwaination factors will be less than those assumed in this guide and must be ettceltted on an indivtdud ease basis using assumptions ccmparabk in conservAISm to those of this "me Ilosre+ cr, as tied designs haft changed. the presence in discharged reds has ineaausal (especially for IFRA cods). It is now expected that fuel pin pressures could be in the range of 1300 -1400 psig.

The impact of elevated suet pin pressure on the pool snubbing DF bas been evahteted with the determination that the Rag. Guide 1.25 value of 133 can be used for fuel pin pressures up to 1500 psig. This detcrnnination is based to the statement in Reg. Guide 1.23 that a 'comparable' level of conservatism is to be used is determining any revision to the DF velum.

Poet Scrubbing OF with Fad Ibis pressure of 12011 prig The Reg. Guide 1.25 poot scrubbing DF of 13) for elemental iodine is believed to be based oa Westinghouse expciimental studies of pool-scrubbing DF that arc reported in WCAP-7828.

In WCAP-7829, Westingboase devetope4 the following equation for elemental iodine pool DF:

Of = p3oasuerd where t

bubble rise time in seconds it bubble diameter in cut au awreai eo.,rs+otoM t

D000040-120, Revision 0 Page 71 of 79 In Table 3-5 of WCAP-7828, the relationship of bubble size and site time to fuel pia pressure

.Is presented: This pressures used in the tilts rings front 100 to 4200 prig. At 1200 prig, the 23 foot depth rise time is 4.7 seconds std the effective babble diameter is 0.71 cm.. Thus:

DF = 7)e.8t3Xa tY G.tl) s 380 The speafacation of a DF of 133 by Reg Guide l.2S represents a factor of raascsvati>m of 4.36 to the WCAP-182$ results.

Fact Scrubbing, DP with W.kvated PW Pb Pressu. *.

Wbilc the maximum eotpected fits! pia pure is between 1300 and 1400 psig, the evalaatiom has considered a fuel pia pressure of tSO0 prig in order to address any (biota pretwo increase that might exceed 1400 prig. As anted above, eifectivo bubble sizes and bubble rise times are provided in WCAP-1128 for a prgseee ango of 100 - 1200 psig. In order to obtain values for these parameters at 1300 prig, the values weto exrrrpolated to 1 500 prig. At a Poet pie pressure of 1500 prig the effect ive babble diameter is 0.645 co and the bubble also time through 23 ft of water is 3.15 seconds. Tbetu:

OF -lotttyttsi)go6.ip q 47.f The cdculated value is a factor of 3.36 times the Reg. Guido 1_2S value of 133.

When considering a fuel pin ptasora of 1100 psig, the level of conservatism associated with for pool sc abbing DF is 4.36, Rounding this gives a general level of conservatism of a factor of 4, his aisomed than -compsrabla, is defined as being any value of conservatism that will sound to 4.0. Using this basis; a comparable lavel of eonsavatiseo would exist as long as the increase in fuel pin pressure did not reduce the calculated AF to below 166_ The calculated DF of 473 for a fuel pin pressure of IS00 psig is just within this criterion. Tbes, a DP of 133 cos continuo to ho used for the PHA ON analysis as long as feel pin pressures do not exceed IS00 psis under the argument o f +maintaiaing. a comparable level ofconservatism.

If there are any questions as the above, please, contact me.

1. L, Grover Cantainme st and Radiological Analysis

-raw &(lot -MC4A a q(.1 ill

`le pr/

tell-ro q s a,^

3y' satscnas<a t#tUaxoxssz 2Y r

ere : ck?.

^s3`3f9a 6444CCO yryt e:o4a I, S. Moeati.m Containment and Radiological Analysis 73m^.st3^rsgfozf':

tea'.

DO00040-120, Revision 0 Page 72 of 79 Memo from D. Lengel to L. Catin "Control Room Velocity Measurement Instrument Uncertainties"

D000040-120, Revision 0 Page 73 of 79 Page I of I CART1N, LUCIUS R From.

LENGEL. DAVID Sent:

Tuesday, November 09, 2004 10:43 AM To:

CARTIN, LUCIUS R Cc:

RICE, CHARLES H

Subject:

Control Room Velocity Measurement Instrument Uncertainties

Lou, Per our discussion yesterday, hero Is the information you requested on Instrument accuracies. I am also including a pdf file of page 9-3 from "Industrial Ventilation. A Recommended Practice". 16;h Edition so you can see dieeiasbsT 1 the numbers I am providing. Note that these values are based on -A standard picot tube with an inclined manometer. Slightly better accuracies can be obtained by using specialty pilot tubes with micro-manometers but l do not think the site uses them.

Outside air 10tH) cfm Duct size 118"x 18" Duct Area 2,25 square feet Duct Velocity 444 fpm As can be seen from the attached pdf file, this velocity is below the useful, range of the pitot tube. Accuracy at 444 fpm can be approximated, at +1-25%. If a hot wire anemometer or deflecting vane anemometer are used, this oeuld be reduced to +/- 20%.

Return air 19143 dm Duct size 42" x 42' Duct Area 12.25 square feet Duct Velocity 1562 fpm At approximately 1550 fpm, the expected error for a pitot tube with Inclined manometer would be approximately

=/. 2%,

If you vary the flow rates for some of your analysis from those listed above, you can use the pdf file information to estimate your expected accuracies.

Let me know if you need any additional information. Thanks.

Dave 11.4)12004

D000040-120, Revision 0 Page 74 of 79 T13STnfG OF VENTILATION SYSTEMS 9-3 The device coeoinle of two concentric tubes, one serving to measure the total or Impact pressure existing in rho air stream, the other to measure the static pressure only. When the annular space and the center tube are connected across a U-tubo manometer, the difference between its tctat pressstro and, the static pressure is indicated on the manometer. Ttiia difference between the total pressure and the static pressure is the velocity pressure.

The velocity preesuro can be used to compute the velocity of the air stream it the density of'the air is kmmn. The following equation can be used:

aser.^ o fee ON '

d t" V 1096 O.73-d;ai..>> ^Iso b Gi e tr^

wham it = detutty hater (Fisnnere 0.14) nor c,lnnhted frmn: d - 400 0 t X 4&92 (far city nit).

where 0

barometric pressure, "8g t - it temperature, r This formula does not consider moirture present In the ale dream. Under conditions of elevated moisture Contpm, obtain the density factor directly from the ptychsomeilric died, page t3-4.2, M g& Whese air is at ttanthed condition Id = LEY), the lint equation above bccomea; V-4006 W Figure 6-161s a velocity vs. velocity pressure table for standard air.. Title 1410 can be used for air at demi-lies other than standard conditions by correcting the measured velocity pressure Inversely as the density factor as in the following equation:

Corrected VP = Measured VP x d The corrected VP can then be used is the Ferocity vs. velocity, pressure table, Figure 0-18, to give the actual velocity at duct conditionm.

From Figure 6.16 It can be seen that at law velocities (below 1000 rpm) the VP values are small (below 0.06' we). The accuracy of the Peet tube is limited at these velocities as the manometer to not precise enough to accurately measure the small pressures. A carefully made and accurately leveled 10-1 inclined manometer calibrated egatset a hook gauge can be read to approximately :t O.OOS' wg. A standard Met tube with an Inclined manometer can be ased with the following degree of accuracy:

VeloM

% Error a) 4000 0.25 3000 0.3 2000 1.0 1000

'4.0 800.

6,0 600 15.0 It can be seen that the use of the Pitt tube to the fiord is limited at velocities loxcr than 600-800 fpm.

Inasmuch as the air flow In the cross-section of a duct is not uniform, it Is neee:,aary to chime: the aver-age by mcanering VP at points in a number of equal arena in the cross-sectlce. The approved method in to make two traverses across the diameter of the duct at right aeglrn to each other. Ttreniy readtites are takers at the center of annular rings of equal area (see Figure 9-3). tables 9-1, 9-2and 0-3 give traverse points`

for various duct diameters. Whenever possible'the traverse should be made 7.5 duet diameters or more downstream from any major air disturbance such as an elbow, hood, branch entry, etc. Where mcazwre-taentn aro made dower 10 dlyturbancoathan 1.3 duct.aiameters;=the. results must.be.consldered aub)ect.to.

some doubt soil cltccked against a;seeead location., If'agreement within 10% is obtafaed,reasonable Ndw racy can,beassumed:aad.the average of the two readings used. Where variation exceeds 10% a third loci-Lion thoisrd 160 ncdected and the two volumes in best agreement averaged and uded.

For round ducts 6s and smaller; at least 6 traverse points should be used. For round ducts larger than 6" diameter, at least 10 traverse points should be employed. For very large duets and discharge stacks with wide variation In velocity, 220 traverse points will Increase the precision of the air flow measurement. Six, ten and twenty point traverse dimensions are given in Tables 9-1, 9.2 and 9-3. Ducts sinalter than 12" diameter will require a Picot tube smaller than the standard 5/16" 0. D.

With square or rectangular duets the procedure Is to divide the cross-section into a number of equal lee-tangulat-areas and measure the velocity pressure at the center of each. The number of readings should not be Mess than 10. However. enough readblgs should be made so the greatest distance between centers is approximately zIx inches. (See Figure 0-4).

Reference:

Industrial Ventilation, A Manual'. of Recommended Practice, 16th Ed' 1980

DC.00040 -120, Revision 0 Page 75 of 79 RADTRAD Dose Conversion Input File Extra Isotopes.inp

D000040-120, Revision 0 Page 76 of 79 FGR11&12 edited to include Xe-131m,.Xe-133m, & Xe-135m See Section 5.2 for complete list of isotopes GONADS BREAST LUNGS 9 ORGANS DEFINED IN THIS FILE:_ ICRP-30 RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 14 NUCLIDES DEFINED IN THIS FILE:

Kr-85 Kr-85m Kr-87 Kr-88 1-131 D

1-132 D

1-133 D

1-134 D

1-135 D

Including:Xe-135m Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m CLOUDSHINE GROUND GROUND GROUND INHALED SHINE 8HR SHINE 7DAY SHINE RATE ACUTE INHALED CHRONIC INGESTION Kr-85 GONADS 1.170E-16 8.121E-14 1.704E-12 2.820E-18-1.000E+00 0.000E+00 0.000E+00 BREAST 1.340E-16 7.891E-14 1.656E-12 2.740E-18-1.000E+00 0.000E+00 0.000E+00 LUNGS 1.140E-16 7.056E-14 1.481E-12 2.450E-18-1.000E+00 0.000E+00 0.000E+00 RED MARR 1.090E-16 6.998E-14 1.469E-12 2.430E-18-1.000E+00 0.000E+00 0.000E+00 BONE SUR 2.200E-16 1.287E-13 2.702E-12 4.470E-18-1.000E+00 0.000E+00 0.000E+00 THYROID 1.180E-16 7.459E-14 1.565E-12 2.590E-18-1.000E+00 0.000E+00 0.000E+00 REMAINDER 1.090E-16 6.941E-14 1.457E-12 2.410E-18-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 1.190E-16 7.603E-14 1.596E-12 2.640E-18-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 1.320E-14 2.304E-11 4.835E-10 8.000E-16-1.000E+00 0.000E+00 0.000E+00 Kr-85m GONADS 7.310E-15 2.594E-12 3.653E-12 1.570E-16-1.000E+00 0.000E+00 0.000E+00 BREAST 8.410E-15 2.527E-12 3.560E-12 1.530E-16-1.000E+00 0.000E+00 0.000E+00 LUNGS 7.040E-15 2.379E-12 3.351E-12 1.440E-16-1.000E+00 0.000E+00 0.000E+00 RED MARR 6.430E-15 2.346E-12 3.304E-12 1.420E-16-1.000E+00 0.000E+00 0.000E+00 BONE SUR 1.880E-14 5.286E-12 7.446E-12 3.200E-16-1.000E+00 0.000E+00 0.000E+00 THYROID 7.330E-15 2.395E-12 3.374E-12 1.450E-16-1.000E+00 0.000E+00 0.000E+00 REMAINDER 6.640E-15 2.313E-12 3.257E-12 1.400E-16-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 7.480E-15 2.511E-12 3.537E-12 1.520E-16-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 2.240E-14 2.247E-11 3.164E-11 1.360E-15-1.000E+00 0.000E+00 0.000E+00 Kr-87 GONADS 4.000E-14 4.962E-12 5.026E-12 7.610E-16-1.000E+00 0.000E+00 0.000E+00 BREAST 4.500E-14 4.740E-12 4.802E-12 7.270E-16-1.000E+00 0.000E+00 0.000E+00 LUNGS 4.040E-14 4.603E-12 4.663E-12 7.060E-16-1.000E+00 0.000E+00 0.000E+00 RED MARR 4.000E-14 4.708E-12 4.769E-12 7.220E-16-1.000E+00 0.000E+00 0.000E+00 BONE SUR 6.020E-14 6.514E-12 6.598E-12 9.990E-16-1.000E+00 0.000E+00 0.000E+00

D000040-120, Revision 0 Page 77 of 79 THYROID 4.130E-14 4.473E-12 4.531E-12 6.860E-16-1.000E+00 0.000E+00 O.000E+00 REMAINDER 3.910E-14 4.590E-12 4.650E-12 7.040E-16-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 4.120E-14 4.773E-12 4.835E-12 7.320E-16-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 1.370E-13 8.802E-11 8.916E-11 1.350E-14-1.000E+00 0.000E+00 0.000E+00 Kr-88 GONADS 9.900E-14 2.278E-11 2.655E-11 1.800E-15-1.000E+00 0.000E+00 0.000E+00 BREAST 1.110E-13 2.177E-11 2.537E-11 1.720E-15-1.000E+00 0.000E+00 0.000E+00 LUNGS.

1.010E-13 2.139E=11 2.493E=11 1.690E-15-1.000E+00 0.000E+00 0.000E+00 RED MARR 1.000E-13 2.190E-11 2.552E-11 1.730E-15-1.000E+00 0.000E+00 O.000E+00 BONE SUR 1.390E-13 2.886E-11 3.363E-11 2.280E-15-1.000E+00 0.000E+00. 0.000E+00 THYROID 1.030E-13 2.012E-11 2.345E-11 1.590E-15-1.000E+00 0.000E+00 O.000E+00 REMAINDER 9.790E-14 2.139E-11 2.493E-11 1.690E-15-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 1.020E-13 2.202E-11 2.567E-11 1.740E-15-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 1.350E-13 5.607E-11 6.534E-11 4.430E-15-1.000E+00 0.000E+00 0.000E+00 1-131 GONADS 1.780E-14 1.119E-11 1.789E-10 3.940E-16-1.000E+00 2.530E-11 4.070E-11 BREAST 2.040E-14 1.082E-11 1.730E-10 3.810E-16-1.000E+00 7.880E-11 1.210E-10 LUNGS 1.760E-14 1.016E-11 1.626E-10 3.580E-16-1.000E+00 6.570E-10 1.020E-10 RED MARR 1.680E-14 1.022E-11 1.635E-10 3.600E-16-1.000E+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 1.810E-14 1.053E-11 1.685E-10 3.710E-16-1.000E+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-14 1.825E-11 2.920E-1.0 6.430E-16-1.000E+00 0.000E+00 0.000E+00 I-132 GONADS 1.090E-13 2.523E-11 2.771E-11 2.320E-15-1.000E+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-15-1.000E+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-11 9.007E-11 7.540E-15-1.000E+00 0.000E+00 0.000E+00 1-133 GONADS 2.870E-14 1.585E-11 6.748E-11 6.270E-16-1.000E+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+00 8.200E-10 4.530E-11 RED MARR 2.770E-14 1.466E-11 6.242E-11 5.800E-16-1.000E+00 2.720E-11 4.300E-11 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-16-1.000E+00 5.000E-11 1.550E-10 EFFECTIVE 2.940E-14 1.509E-11 6.425E-11 5.970E-16-1.000E+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-15-1.000E+00 4.250E-12 1.100E-11 BREAST 1.440E-13 1.145E-11 1.147E-11 2.520E-15-1.000E+00 6.170E-12 1.170E-11 LUNGS 1.270E-13 1.100E-11 1.102E-11 2.420E-15-1.000E+00 1.430E-10 1.260E-11 RED MARR 1.250E-13 1.127E-11 1.129E-11 2.480E-15-1.000E+00 6.080E-12 1.090E-11 BONE SUR 1.960E-13 1.568E-11 1.571E-11 3.450E-15-1.000E+00 5.310E-12 9.320E-12 THYROID 1.300E-13 1.127E-11 1.129E-11 2.480E-15-1.000E+00 2.880E-10 6.210E-10 REMAINDER 1.220E-13 1.091E-11 1.093E-11 2.400E-15-1.000E+00 2.270E-11 1.340E-10 EFFECTIVE 1.300E-13 1.150E-11 1.152E-11 2.530E-15-1.000E+00 3.550E-11 6.660E-11 SKIN(FGR) 1.870E-13 4.477E-11 4.485E-11 9.850E-15-1.000E+00 0.000E+00 0.000E+00 1-135

D000040-120, Revision 0 Page 78 of 79 GONADS 8.078E-14 3.113E-11 5.489E-11 1.599E-15-1.000E+00 1.700E-11 3.610E-11 BREAST 9.143E-14 2.971E-11 5.240E-11 1.526E-15-1.000E+00 2.340E-11 3.850E-11 LUNGS 8.145E-14 2.886E-11 5.089E-11 1.482E-15-1.000E+00 4.410E-10 3.750E-11 RED MARR 8.054E-14 2.965E-11 5.228E-11 1.523E-15-1.000E+00 2.240E-11 3.650E-11 BONE SUR 1.184E-13 3.983E-11 7.024E-11 2.046E-15-1.000E+00 2.010E-11 3.360E-11 THYROID 8.324E-14 2.852E-11 5.030E-11 1.465E-15-1.000E+00 8.460E-09 1.790E-08 REMAINDER 7.861E-14 2.883E-11 5.084E-11 1.481E-15-1.000E+00 4.700E-11 1.540E-10 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-15-1.000E+00 0.000E+00 0.000E+00 Xe-131m GONADS 4.570E-16 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 BREAST 6.020E-16 0.000E+00 0.000E+00 O.000E+00 0.000E+00 0.000E+00 0.000E+00 LUNGS 2.670E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RED MARR 2.270E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BONE SUR 1.060E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 THYROID 3.910E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 REMAINDER 2.710E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 EFFECTIVE 3.890E-16 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 4.820E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-133 GONADS 1.610E-15 1.465E-12 2.052E-11 5.200E-17-1.000E+00 0.000E+00 0.000E+00 BREAST 1.960E-15 1.505E-12 2.107E-11 5.340E-17-1.000E+00 0.000E+00 0.000E+00 LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-1.000E+00 0.000E+00 0.000E+00 RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.000E+00 0.000E+00 0.000E+00 BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.000E+00 0.000E+00 0.000E+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.000E+00 0.000E+00 0.000E+00 REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.000E+00 0.000E+00 0.000E+00 Xe-133m GONADS 1.420E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BREAST 1.700E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LUNGS 1.190E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RED MARR 1.100E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BONE SUR 3.230E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 THYROID 1.360E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 REMAINDER 1.150E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 EFFECTIVE 1.370E-15 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 1.040E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-135 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.000E+00 0.000E+00 0.000E+00 BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.000E+00 0.000E+00 0.000E+00 LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.000E+00 0.000E+00 0.000E+00 RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-1.000E+00 0.000E+00 0.000E+00 BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.000E+00 0.000E+00 0.000E+00 THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.000E+00 0.000E+00 0.000E+00 REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.000E+00 0.000E+00 0.000E+00 EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.000E+00 0.000E+00 0.000E+00 SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-1.000E+00 0.000E+00 0.000E+00 Xe-135m GONADS 2.000E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BREAST 2.290E-14 0.000E+00 0.000E+00 0.000E+00*O.000E+00 0.000E+00 0.000E+00 LUNGS 1.980E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RED MARR 1.910E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BONE SUR 3.500E-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

DC00040-120, Revision 0 Page 79 of 79 THYROID 2.040E-14 0.000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00.0.000E+00 REMAINDER 1.890E-14 0.000E+00 0,000E+00 0.000E+00 0.000E+00 O.000E+00 0.000E+00 EFFECTIVE.2.040E-14 O.000E+00 0.000E+00 0.000E+00 0.0.00E+00 0..000E+00 0..0.00E+00 SKIN(FGR) 2.970E-14 O.000E+00 0.000E+00 0.000E+00 0.000E+00 0,000E+00 0.000E+00

TECHNICAL WORK RECORD Originator:

Michael Waselus,,,,,,,,,J Date:

07/30/2012 System:

N/A Project Title Verification of D000040-120, RO ECR 50786 Page 1

of 3

1.0 Purpose

This TWR is developed to document the verification of D000040-120, R0, "Fuel Handling Accident - TSC."

2.0

Reference:

Calculation D000040-120, Revision 1, "Fuel Handling Accident - TSC."

3.0 Discussion

The verification of the calculation is to assure that the calculation has been completed lAW ES-412. The verification is performed lAW ES-110. ES-110, Attachment III is included as Attachment 1 to this TWR.

The verification included check of input, mathematical manipulations, computer code input/output and results. The RADTRAD computer code was utilized in the analysis. RADTRAD is a validated and verified code for nuclear use IAW WorleyParsons QA procedures. There are no assumptions in the calculation requiring future confirmation.

4.0 Comments

Technical comments resulted from the review.

1.

None Editorial comments:

1.

Add FSAR Section 15.4.5 to Affected Documents 2.

Add VC Summer Calculation D000040-102, R1, "Fuel Handling Accidents - AST to References.

3.

Add EAB and LPZ doses to Summary of Results to compare to results in D000040-102.

4.

Miscellaneous small typographical changes provided to originator incorporated.

5.

Successfully incorporated David McCreary comments.

5.0 Results

The verifier comments have been resolved and the results of the calculation are acceptable for use.

TECHNICAL WORK RECORD Originator:

Michael Waselus Date:

07/30/2012 System:

N/A Project Title Verification of DC00040-120, RO ECR 50786 Page 2

ES-110 ATTACHMENT III PAGE 1 OF 2 REVISION 2 VERIFICATION RECORD: CALCULATION Calculation #

DC00040-120 Revision 0 The following questions, as a minimum should be answered for calculation verification.

Yes N/A

q

q Have inputs, including codes, standards, regulations, requirements, procedures, data and engineering methodology been correctly selected and applied?

Has the calculation been developed in accordance with applicable station procedures (e.g., ES-412).

Is the plant design basis/criteria maintained?

Have assumptions been identified, especially those requiring later confirmation?

Have references been properly identified and complete?

Have the calculation, results, tables and figures been reviewed with regard to numerical accuracy, units and consistency?

Has the calculation been developed/revised in a clear and understandable manner as to not require recourse to the originator?

Is the output reasonable compared to the input?

Do the diagrams or models depicted represent the physical situation correctly and incorporate necessary features for a correct analysis?

Has the calculation cover page been completed in an accurate manner?

Are the sign conventions used in figures and equations consistent?

Is consistent nomenclature used throughout the calculation (e.g., figures, tables)?

Are symbols used on figures and in the text defined?

Are concurrent in-process revisions been addressed and coordinated with this revision?

Has the Calculation Index been updated?

Additional considerations (see attached TWR)?

TECHNICAL WORK RECORD Originator:

Michael Waselus Date:

07/30/2012 System:

N/A Project Title Verification of DC00040-120, RO ECR 50786 Page 3

of 3

ES-110 ATTACHMENT III PAGE 2 OF 2 REVISION 2 VERIFICATION RECORD: CALCULATION Calculation #

DC00040-120 Revision 0 CALCULATIONS UTILIZING COMPUTER PROGRAMS:

El 0

q Has the program been appropriately defined, including the version?

Is the basic methodology used by the program appropriate for the calculation?

Has the appropriate computer program been used?

Has the calculation been performed within the known limits of the program?

Has the computer program been verified and validated in accordance with SAP-1040? Validated by WorleyParsons.

Has the program been defined, controlled, and benchmarked so that the results reported are traceable to a particular version of the program and a particular set of input data?

Have limits for the program been defined, as appropriate?

Comments have been included and resolved.

Is the Validation Data set for the application complete, and provide repeatable results?

M. M. Waselus/

07/30/2012 Verifier's Printed Name Verifier's Signature Date

ES-0110 ATTACHMENT XVI PAGE 1 OF/Z' D ^'?r, REVISION 2

$fof,i REVIEW CONSIDERATIONS: OWNER'S ACCEPTANCE REVIEW ECR/Document Number: DC00040-079, DC00040-118 Through -123 Project

Title:

Review of New NOB TSC Dose Calculations The following questions should be considered, as a minimum, during the performance of an Owner's Acceptance Review of vendor developed engineering documents.

Yes N/A

q

q Is the technical information/design complete, consistent, and correct for the activity under review?

Were inputs, including codes, standards, and regulatory requirements correctly selected and applied?

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

Is the document/package developed in a clear and understandable manner?

Is the plant design basis/criteria maintained?

q Are references properly identified and complete?

El 0

Were design considerations from EC-01, Attachment I and II adequately addressed/incorporated?

q Were technical, design, program or procedure requirements adequately add ressed/incorporated?

q Have applicable construction and operating experiences been considered?

q Were designs developed in accordance with good engineering practices and established ES guidance documents?

Have impacted documents, databases (EC-02) and equipment changes been identified?

q Is the document/package developed in accordance with applicable station procedures (e.g., SAP-133, ES-453, ES-455)?

q Is the document/package developed in a clear and understandable manner as to not require recourse to the Originator?

D

ES-0110 ATTACHMENT XVI PAGE 2OF,'f D.P; REVISION 2 i1-VIII Yes N/A Does the design meet interfacing organizations operational/maintenance requirements?

11 Is technical information adequate to perform the task?

Is the acceptance criteria adequate for the activity under review?

Is the post modification testing adequate to confirm the design?

Has the 10CFR50.59 Review Process been completed, if required?

For work performed in accordance with VC Summer Nuclear Station Procedures, the procedure forms must be signed by the originator and if not qualified must be co-signed by a qualified person. Check the qualifications of the contractor personnel signing the procedure forms.

Yes No Are contractor personnel signing the VCSNS procedure forms qualified under a vendor qualification program or the VCSNS Nuclear Training Manual for those procedures?

q If not have the VCSNS forms been co-signed by a person qualified to the applicable procedure?

Technical Reviews

q Are all technical reviews complete and all comments resolved to the satisfaction of the commenter?

TECHNICAL REVIEW: Check all blocks that apply q Principal Piping Engineer q

Principal Engr Analysis Engineer q

Principal I&C Engineer q

Principal Mechanical Engineer q

Principal Civil Engineer q

Principal PSA Engineer q

Principal Nuclear Fuels Engineer q

Principal Digital Engineer q

Principal Electrical Engineer q

Principal EQ Engineer q

Principal Fire Protection Engineer q

MAnalysis Engineer Dave McCreary q

q q

q Dave McCreary ran Reviewer's Printed Name Reviewer's Sigr'iature Date D

0110 afi xv1, Detailed Owners Acceptance Review Notes PI`

There are three general comments in all of the dose calculations that should be addressed:

1)

The initiation of the HVAC "Emergency Mode" would only be manually. There are statements in the calculations of SI signal initiation. These should be removed to avoid confusion with the Unit 1 Control Room Habitability Envelope and it's automatic Emergency Mode initiation on an SI signal.

SPONSE:

atements' re"garding Sl signals wtl e.remove 2)

The 1000 cfm allotted for TSC "inleakage" isn't applicable in these scenarios since it is very conservatively assumed that none of the air flowing through the TSC is filtered or recirculated. Therefore, 13,000 cfm of unfiltered outside air is flowing into the TSC and out of the TSC. The discussions should be cleaned up to state that the 13,000 cfm assumed conservatively bounds the expected design flow rate value of 12,000 cfm, and that the doses calculated due to assuming no filtration throughout the accident is very conservative since the TSC filtration capability and isolation times are currently unknown.

SPON crm assume V

filtration throe ree as,note conservativell oses are conservative out.the acciden esign flow rate value of calculated assuming norc credit for refer. not-to state"that the TSCfltration cababili currently unknown There is a;;P&IDshowing filters an i

assumed an operator action such as 30 minutes f

3)

Suggest not listing procedure revision levels in the verification TVVR's. ES-412 and

-110 have been updated.

SPOON RESPONS below:

ree to,delete revision levels:

individual co'mmen Main Steam Line Break, DC00040-118, Rev. 0:

e revise.,d :to "tat";1,000 comments/corrections note 1.

Follows same format and methodology as in MSLB dose calculation D000040-099 for CR/EAB/LPZ.

2.

Table of Contents needs to be updated for page number corrections.

3.

Section 5.3 should be revised for the general comments above.

Es'.-alo xvs.

Locked Rotor, DC00040-119, Rev. 0:

pf lc.

4.

Follows same format and methodology as in LR dose calculation 0000040-100 for CR/EAB/LPZ.

Sections 2.16 and 5.10 should be revised for the general comments above.

5.

References 4.11 and 4.14 are the same. Per DI-5.10, Ref. 4.11 should be same reference as used in DC00040-118 Ref. 18.

6.

Reference 4.17 is up to Rev 3... Affects DI-5.9 (10gpm value is now 30gpm), but calc uses the correct mass rate so no change in results.

Fuel Handling Accident, DC00040-120, Rev. 0:

7.

Follows same format and methodology as in Fuel Handling dose calculation DC00040-102 for CR/EAB/LPZ.

8.

Sections 2.15 and 5.12 should be revised for the general comments above.

SGTR, D000040-121, Rev. 0:

9.

Follows same format and methodology as in SGTR dose calculation D000040-098 for CR/EAB/LPZ.

10.

Section 5.3 should be revised for the general comments above.

LOCA,. DC00040-122, Rev. 0-11.

Follows same format and methodology as in LOCA dose calculation D000040-097 for CR/EAB/LPZ.

12.

Section 5.7 should be revised for the general comments above.

CREA, DC00040-123, Rev. 0:

13.

Follows same format and methodology as in CREA dose calculation D000040-101 for CR/EAB/LPZ.

14.

References 4.11 and 4.12 are the same. Per DI-5.10, Ref. 4.11 should be same reference as used in DC00040-118 Ref. 18.

15.

Section 5.10 should be revised for the general comments above 7

/1-10C, Asev? rt.1ej-

ML14324A324

Text

Description:

SUMMARY

1.0 INTRODUCTION

4.0 REFERENCES

SUMMARY

1.0 INTRODUCTION

4.0 REFERENCES

SUMMARY

Subject:

Reference:

1.0 Purpose

Reference:

3.0 Discussion

4.0 Comments

5.0 Results

Title:

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