Text

Calculation 32-5052589-01, PNPS -Radiological Consequences of Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 Mwt).
	ML043650061
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Site:	Pilgrim
Issue date:	12/15/2004
From:	Hamawi J; AREVA
To:	; Office of Nuclear Reactor Regulation
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Attachment 2 to 2.04.115 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Prooosed Amendment to the Technical SDecifications Areva Document No. 32-5052589-01, "RadiologicalConsequences of a Design-Basis Fuel Handling Accident Based on the Alternate Source Term Methodology', (141 pages)

20032-33 (6/23/2004)

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AR EVA Document Identifier 32-5052589-01 Title PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term TItle Methodology (2038 MWt)

PREPARED BY: REVIEWED BY:

METHOD: Z DETAILED CHECK I IDEPENDET CALCULATION NAME John N. Hamawi, Ph.D. NAME Jo-Ann Pelczar SIGNATURE i ' SIGNATURE - A TmTLE l ting Radiological Eng. DATE /CZ ILE Ra oloal Engineer DATE COST REF. TM STATEMENT:

CENTER 41759 PAGE(S) 22-23 REVIEWER INDEPENDENCEi CZ PURPOSE AND

SUMMARY

OF RESULTS:

Purpose The objective of this calculation is to determine the radiological consequences of a design-basis fuel handling accident based on the Alternative Source Term methodology. The receptors of interest are inthe main control room and offsite (at the Exclusion Area Boundary and the Low Population Zone).

Results A summary of the results, based on a minimum of 24-hr decay prior to movement of irradiated fuel, is presented in the following table.

LOCATION Expopsure Unfiltered Outside TEDE Dose Regulatory Limit Percent of Interval Air Intake Rate (rem) (rem) Regulatory Limit Control Room 30 days 1000 cfm 2.846 5 56.9 9000 cfm 2.863 5 57.3 EAB 2 hrs N/A 1.439 6.3 22.8

LPZ 30 days N/A I 0.0920 6.3 1.46 All doses are the result of unfiltered ground-level releases to the environment via the RB Vent, with no credit taken for the operation of the Standby Gas Treatment System (which is for filtered activity releases to the environment via the main stack). Further details are provided in the Summary Section (Sec. 2). Itis concluded that the CR TEDE dose documented inthis calculation is bounding for any outside air kow that may be assumed to enter the CR. As such, this calculation will not be affected by the results of the up-coming CR inleakage testing mandated by NRC Generic letter 2003-01 (Ref. 3),

and no revision will be necessary.

This calculation Issafety-related and was prepared under the AREVA Framatome ANP Quality Assurance Program.

Revision 01 The purpose of this revision is to incorporate client comments. See page 2 for further details. There are no changes inthe results.

THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFETY.

RELATED WORK CODE(VERSIONIREV CODE/VERSION/REV ELISA-2, Version 2.2 YES Z NO Framatome ANP, Inc., an AREVA and Siemens company Page I of 141

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 ARE VA Prepared by: John N.Harnawi Page 2 RECORD OF REVISIONS Revision 01 (December 2004) - Incorporation of Client Comments (1) Changed the calculation No. from 32-5052589-00 to 32-5052589-01, inall pages.

(2) Moved the 'Record of Revisions' from page 4lo page 2,and renumbered the pages where necessary.

(3) Pg. 1, Purpose and Summary of Results section:

(a) Changed column heading for 'Outside Air Intake Rate' to read 'Unfiltered Outside Air Intake Rate."

(b) Added another column for 'Exposure Interval.'

(c) Added note below table stating that all doses are the result of unfiltered ground-level releases to the environment via the RB Vent, with no credit taken for the operation of the Standby Gas Treatment System (which isfor filtered activity releases to the environment via the main stack).

(d) Added a statement identifying the purpose of the revision.

(e) Did minor rewording to fit all the information within the alloted space.

(4) Pg. 5,Table of Contents: Moved the 'Record of Revisions' section from Page 4 to Page 2,and renumbered Section Nos. 1.1 through 1.5 to be sequential. All other page numbers, and the total number of pages inthe calculation remain the same.

(5) Pg. 7, under Atmospheric Dispersion Factors, Item (a): Changed '6 years' worth of hourly meteorological data collected on site' to '5 years' worth (1996-2000) of hourly meteorological data collected on site."

(6) Pg. 8, under Computing Environment, 2nd paragraph: Changed 'un uncontrolled copy' to 'an uncontrolled copy.'

(7) Pg. 1O, Item (k): Changed "The 9000 cfm is approximates' to 'The 9000 cfm approximates," and ' to evaluated the impact ' to ' to evaluate the impact.'

(8) Pg. 10, inTable 2.1:

(a) Changed column heading for 'Outside Air Intake Rate' to read, 'Unfiltered Outside Air Intake Rate' (b) Included the following sentence under Item (a), following the table: 'The radiological consequences of an FHA were based on unfiltered ground-level releases to the environment via the RB Vent, with no credit taken for the operation of the Standby Gas Treatment System (which is for filtered activity releases to the environment via the main stack).'

(9) Pg. 12, Section 3: The list of assumptions were renumbered to eliminate the two (b)s.

(10) Pg. 14, Table 3.1, Note (c): Reworded the 3rd sentence from:

'In addition, releases via the main stack are not feasible since the Standby Gas Treatment System (SGTS) is not activated' to OIn addition, releases via the main stack are feasible if the Standby Gas Treatment System (SGTS) isinitiated and functioning properly. However, credit for SGTS filtration and release to the environment, via the main stack as an elevated release, was not assumed in this analysis. Unfiltered ground-level releases via the RB Vent produced the greatest radiological impact in the CR, at the EAB, and at the LPZ, without exceeding the regulatory dose limits.'

22410-3 (5/10/2004) 1of 2 ADESIGN VERIFICATION CHECKLIST IAREVA Document Identifier 32-5052589-01 - Page 3 of 141 PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Title Alternative Source Term Methodology (2038 MWt)

1. Were the inputs correctly selected and incorporated into design or analysis? Y [ N El N/A

2. Are assumptions necessary to perform the design or analysis activity adequately [2 Y E N 0 N/A described and reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?

3. Are the appropriate quality and quality assurance requirements specified? Or, for [i Y N ° N/A documents prepared per FANP procedures, have the procedural requirements been met?

4. If the design or analysis cites or is required to cite requirements or criteria based upon Y El N a N/A applicable codes, standards, specific regulatory requirements, including issue and addenda, are these properly identified, and are the requirements/criteria for design or analysis met?

5. Have applicable construction and operating experience been considered? [i Y El N [O N/A

6. Have the design interface requirements been satisfied? E Y O N E[l N/A

7. Was an appropriate design or analytical method used? d Y O N O N/A

8. Is the output reasonable compared to inputs? ILI Y ON O N/A

9. Are the specified parts. equipment and processes suitable for the required application? a Y E N d N/A

10. Are the specified materials compatible with each other and the design environmental 0 Y 0 N N/A

.conditions to which the material will be exposed? -

11. Have adequate maintenance features and requirements been specified? Y N N/A

12. Are accessibility and other design provisions adequate for performance of needed E Y 0 N N/A maintenance and repair?

13. Has adequate accessibility been provided to perform the in-service inspection expected 0] Y 0 N N/A to be required during the plant life?

14. Has the design properly considered radiation exposure to the public and plant ° Y 0 N j NIA personnel?

15. Are the acceptance criteria incorporated in the design documents sufficient to allow a Y El N Ei N/A verification that design requirements have been satisfactorily accomplished? _

16. Have adequate pre-operational and subsequent periodic test requirements been appropriately specified?

0 Y 0 N 16 NIA

17. Are adequate handling, storage, cleaning and shipping requirements specified? E *D N Ski N/A

18. Are adequate identification requirements specified? EO Y O N Ed N/A

19. Is the document prepared and being released under the FANP Quality Assurance 0' Y E3 N D N/A Program? If not, are requirements for record preparation review, approval, retention, etc., adequately specified?

Frarnatome ANP, Inc, an AREVA and Siemens company

22410-3 (5/10/2004)2 rf2 Pt DESIGN VERIFICATION CHECKLIST AREVA Document Identifier: 32-5052589-01 - Page 4 of 141 Comments: Oq(

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Verified By: Jo-Ann Pelczar .4/4/L (First, MI, Last) Printed / Typed Name Signature Date Framatome ANP, Inm, an AREVA and Siemens company \,_/

ABasedA PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 5 TABLE OF CONTENTS Page No.

Calculation Summary Sheet ...................................................................... 1 Record of Revisions ........ .............................................................. 2 Design Verification Checklist ...................................................................... 3

1. Problem Description.6 1.1 Purpose/Objective .. 6 1.2 Method of Solution and Software Usage .6 1.3 Identification of Key Assumptions. ................... 8..............

1.4 Acceptance Criteria .. 8 1.5 Quality Assurance ........... -.8 8..............

2. Surnmaryof Results.9

3. Design Input and Assumptions.12

4. Analyses and Results.18 4.1 Sourcesult Term....18 4.2 Results ...................................................................... 20 References................................................................................................................................................................ 22 ATTACHMENTS A. Alternative FHA Analysis Based on RADTRAD .24 B. The Finite-Cloud Gamma XIQ .26 C. ELISAt 2 Features at aGlance.29 D. Copies of Selected References.31 E Uist of Computer Runs ................................. 38-14 1

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWQ)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 6 AR EVA

1. PROBLEM DESCRIPTION 1.1 Purpose/Objective The objective of this calculation is to determine the radiological consequences of a design-basis Fuel Handling Accident (FHA) at the Pilgrim Nuclear Power Station (PNPS) based on an open containment and the Alternative Source Term (AST) methodology (Ref. 1). The receptors of interest are in the main Control Room (CR), at the Exclusion Area Boundary (EAB), and at the Low Population Zone (LPZ).

It is Entergy's intention to use the results of this calculation as a basis for changes to the plant Technical Specifications with respect to changes in the configuration of the secondary containment during refueling operations, and for submittal of a Proposed License Amendment to the Nuclear Regulatory Commission.

Once approved for implementation, this calculation will supercede the existing FHA calculation(s) making use of the classical analytical approach (TID-14844, Ref. 2)and Reg. Guide 1.25 (Ref. 22)

This calculation forms part of the deliverables listed in the contract between ENTERGY and AREVA/Framatome ANP (Ref. 4).

1.2 Method of Solution and Software Usage Source Term The core radionucide inventory was extracted from Ref. S. This inventory isbounding for the following core parameters:

Power level: c 2038 MWt Fuel enrichment: 3.9 - 4.6 w/o U-235 Core loading: 101.8 - 105.56 MTU (metric tons of uranium)

Bumup: 5 -60 GWDIMTU For each radionuclide, the core inventory corresponds to the bounding value within the listed ranges of enrichment, core loading, and burnup. Ingeneral, and based on the tabulations in Ref. 5,the noble-gases and halogens of interest in design-bases calculations peak at the following bumups:

Low bumup: 1-133,1-134,1-135,1-136 Kr-83m, Kr-85m, Kr-87, Kr-88, Kr-89, Kr-90 Xe-1 33, Xe-1 35, Xe-1 37, Xe-1 38 High bumup: 1-131,1-132 Kr-85 Xe-131m, Xe-133m, Xe-135m With respect to enrichment, the grouping isas follows:

Low enrichment: lodines, and xenons (except Xe-135)

High enrichment: Kryptons, and Xe135

A ARE VA A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Mcident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 7 The corresponding inventory inthe peak-powered fuel rods (which are assumed to get damaged as a result of the postulated FHA) was calculated by applying an adjustment factor to the inventory of an average fuel rod inthe core. This adjustment factor isequal to the ratio of the peak-to-average fuel-rod power levels (i.e., to the radial peak factor). For the noble gases and halogens of interest, this approach leads to practically the same results (within a few percent) as an ORIGEN-2 computer run which specifically models the peak-powered fuel rods, with two exceptions, as follows:

(1) Kr-85 is overestimated by the extrapolation approach since i isvery long lived and iRs inventory increases with bumup (i.e., external application of the radial peaking factor corresponds to a similar increase in the bumup).

(2) Xe-135 isalso overestimated because of iRs high neutron-absorption cross-section (i.e., external application of the radial peaking factor does not alter the neutron flux and thus leads to an underestimation of the loss of Xe-1 35 through neutron absorption).

Nonetheless, for an FHA, Kr-85 contributes only about 2 % of the total TEDE dose, and Xe-135 is not a significant contributor since most of it decays away prior to the postulated accident.

Radiological Evaluation The radiological evaluation of the postulated FHA was carried out through use of the ELISA-2 computer code (Ref. 6)in the FANP Computer Software Index (software control library). An alternative analysis (non-safety related), making use of the NRC RADTRAD computer code (Ref. 7), is presented inAttachment Afor informational purposes.

A brief description of ELISA-2 ispresented inAttachment C. It isnoted that the dose conversion factors in ELISA-2 are from Federal Guidance Reports 11 and 12 (Refs. 13 and 14). Dose rates and cumulative doses will be computed for each organ, skin and air, however only the Total Effective Dose Equivalent (TEDE) will be reported, as required for implementation of the AST. Doses to other organs and skin can be found inthe ELISA-2 outputs inAttachment E.

Atmospheric Dispersion Factors The atmospheric dispersion factors were extracted from Ref. 9. They were based on the following:

(a) 5 years' worth (1996-2000) of hourly meteorological data collected on site, (b) The ARCON 96 computer code (Ref. 20) for atmospheric transport of the released radioactivity to the control room fresh air intake (based on the guidance in Reg. Guide 1.194, Ref. IO), and (c) The AEOLUS-3 computer code (Ref. 11) for atmospheric transport of the released radioactivity to offsi-e receptors (which implements the guidance in Regulatory Guide 1.145, Ref. 23)

PNPS -Radiological Consequences of aDesign-Basis Fuel Handling Accident Document ID32.5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

ARE VA Prepared by: John N.Hamawi Page 8 Computing Environment All ELISA-2 computer runs were carried out on the HP 90001785 CPU running HP UX B.1 0.20. ELISA-2 has been used in analogous applications at many nuclear power plants. There are no software errors that affect its application in the present calculation. The CSI records cite QA verifications for ELISA-2, Version 2.2.

[The non-safety-related RADTRAD computer runs inthe alternative analysis presented in Attachment A (for informational purposes) were carried out on a personal computer using an uncontrolled copy of the code.]

1.3 Identification of Key Assumptions A key assumption isany assumption or limitation that must be verified prior to using the results and/or conclusions of a calculation for asafety-related task. There are no key assumptions inthe present calculation.

1.4 Acceptance Criteria The basic radiological acceptance criteria associated with the AST methodology are spelled out in 10 CFR 50.67, and amount to 25 rem TEDE for ffs'ite recepto'rs-and 5 rem for control room personnel.' These criteria, however, are for evaluating potential reactor accidents of exceedingly low occurrence probability and low risk of public exposure to radiation. For events with higher probability of occurrence, such as a fuel handling accident, the acceptance criteria for the offsite receptors are more stringent, while that for the control room operators remains the same. The applicable AST criteria for an FHA are as follows (Ref. 1, and 10 CFR 50.67):

Exclusion Area Boundary (EAB): 6.3 rem TEDE Low Population Zone (LPZ): 6.3 rem TEDE Control Room (CR): 5.0 rem TEDE 1.5 Quality Assurance This work was performed under Framatome's Quality Assurance Program and is appropriate for safety-related design work. Framatome Procedure 0402-01 (Preparing and Processing FANP Calculations) was followed.

PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by: John N.Hamawi Page 9

2.

SUMMARY

OF RESULTS The present calculation dealt with the radiological evaluation of a design-basis fuel handling accident (FHA) taking place at the Pilgrim Nuclear Power Station, based on an open containment and on the AST methodology (Ref. 1). The accident scenario consisted of the following:

(a) The reactor has been operating at full power (2038 MWt) for an extended period of time.

(b) The reactor is shutdown, refueling operations are initiated and an FHA takes place at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown.

(c) The accident involves the dropping of a GE-14 fuel assembly in the refueling cavity (with a depth greater than 23 ft), and the ensuing rupture of 151 fuel rods (all the rods in the fallen assembly and other rods in impacted assemblies).

(d) All failed rods are peak powered, wih a radial peaking factor of 2.1.

(e) All activity within the gaps of the failed fuel rods is released to the refueling cavity water. The released activity corresponds to 8 % of the entire inventory of 1-131 in the rods (i.e., within the fuel matrix and gaps), 10 % of the Kr-85, 5 % of the remaining halogens and noble gases, and 12 %of the alkalis (Cs and Rb).

(f) All the noble gases and (1/200)th of the halogens escape from the pool and are released to the refueling level. All the alkalis are retained by the pool. The halogen composition above the pool is 57 % in elemental form and 43 %in organic form'.

(g) The reactor building is assumed to be open during the refueling operations, with the normal ventilation on, such that all releases to the environment would be via the Reactor Building vent. This is the most restrictive scenario with respect to the radiological impact.

[Note: Potential releases via the Truck Lock would lead to lower CR doses due to the lower atmospheric dispersion factor from the Truck Lock to the CR fresh air intake (see Table 3.3). In addition, potential leakage via the RB siding is very unlikely in view of the structural design of the RB walls above the refuel level floor (columns of structural steel and 6- pre-cast concrete wall panels with structural steel bracing and caulking), and the recent improvements for leak-tightness2.]

(h) Potential halogen plateout within the refuel floor walls and the vent ductwork is not credited.

1 The halogen composition has no impact inthis analysis since there isno filtration credit.

2 The Reactor Building pre-cast panels span horizontally between columns, are connected to the columns by embedded steel angles and studs, and the panels and angles are welded to the column flanges. The pre-cast panels along with the interior caulking of the horizontal joints minimize leakage out of the secondary containment during activation of the Standby Gas Treatment system.

Exterior caulking of the oints provides afurther passive caulking and provides a leak tightness function. To maintain secondary containment integrity, PNPS Nuclear Change ER # 03120058 (Ref. 19) was recentiy issued for the re-sealing of joints inthe pre-cast panels from the refuel floor elevation 11'r-o to the top of the panels at elevation 165'-11 -.

PNPS -Radiological Consequences of aDesign-Basis Fuel Handling Accident Document ID32-5052589-01 A Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Page 10 AR EVA (i) Release to the atmosphere iswithin a period of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (analytically based on an assumed air exchange rate of 4 air changes per hour, leading to 48.7 %of the airborne activity getting released within 10 minutes, 86.5 %within 30 min, 99.2 %within 1hour, and 99.97 %within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

0) The atmospheric release is assumed to be at the actual vent elevation for the CR analysis (based on Reg. Guide 1.194, Ref. 20), and at ground-level for the off-site receptors.

(k) The control room ventilation system isassumed to remain in the normal operating mode during the entire exposure interval (30 days). Two air flows were considered in the analysis: 1000 cfn and 9000 cfm. The 9000 cfm approximates a bounding value which includes the maximum air flow via the fresh air intake and additional flow from surrounding areas as a result of ingress, egress and leakage. The 1000 cdm isan arbitrarily selected low flow to evaluate the impact of the flow rate on the CR dose.

(M) Breathing rates, and control room occupancy factors are as given in Reg. Guide 1.183 (Ref. 1).

A summary of the results ispresented inTable 2.1.

Table 2.1 Pilgrim Station - Fuel Handling Accident Dose Results - AST Methodology

[From Table 4.2]

Exposrer Unfiltered TEDE Dose Regulatory Percent of LOCATION Inexpsrea Outside Air TEEroem Limit Regulatory Inevl Intake Rate (e)(rem) Limit 1000 cfn 2.846 5 56.9 Control Room 30 days 9 19000 cfm 2.863 1 5 -1 57.3 EAB 2 hrs N/A 1.439 6.3 22.8 LPZ 30 days N/A 0.0920 6.3 1.46 The following are noted:

(a) The radiological consequences of an FHA were based on unfiltered ground-level releases to the environment via the RB Vent, with no credit taken for the operation of the Standby Gas Treatment System (which isfor filtered activity releases to the environment via the main stack). All TEDE doses are within the acceptance criteria given in Sec. 1.4. The highest dose is2.86 rem to the CR operators (57 % of the 5 rem limit), for the assumed unfiltered intake flow of 9000 cfm (via the fresh air intake vent, and from adjacent areas as a result of ingress and egress and leakage).

(b) The results inTable 2.1 are bounding for the following core parameters:

Power level: 2038 MWt Fuel enrichment: 3.9 - 4.6 w/o U-235 Core loading: 101.8 - 105.56 MTU (metric tons of uranium)

Bumup: 5 - 60 GWD/MTU

AABased on the Alternative Source Term Methodology (2038 MWI)

PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID32-5052589-01 ARE VA Prepared by, John N.Hamawi Page 11 Minimum decay time prior to fuel movement: 24 hrs (c) The inhalation pathway contributes about 98 %of the CR total TEDE dose. At the EAB and the LPZ, the corresponding contributions are about 83 % and 65 %, respectively (See Table 4.2).

(d) Based on scoping analyses, use of the gamma (XIQ) reduces the EAB TEDE dose by 0.33 rem and the LPZ dose by 0.0016 rem; the dose reduction at the LPZ isless because the gamma (X/Q)s and the concentrations (XIQ)s at the LPZ are numerically close (inview of the plume size at the LPZ). [See Table 3.3 for the (X/Q)s, and also Table A.1 for the EAB doses.]

(e) Ingeneral, the CR FHA dose increases with increasing fresh air flow, but soon reaches amaximum value. Ahigh flow rate leads to an increase inthe amount of radioactivity which enters the control room, but also leads to an increase in the rate at which the contaminated air isexhausted from the control room. Thus, the airborne concentration inthe CR and the ensuing dose rate Increase with Increasing intake flow, but the exposure interval decreases. These counteracting effects result in a minimal change on the integrated dose. Inthe present applicaton, the difference inthe CR dose between afresh air intake flow of 1000 and 9000 cfmris only (2.863 -2.846) = 0.017 rem.

(D) According to the AST methodology, the only regulatory dose limit isto the TEDE. Doses to other organs (thyroid, lung, gonads, etc.), skin (beta +gamma), gamma air, and beta air, have also been calculated, and may be found inthe ELISA-2 computer outputs in Attachment E of this calculation.

(g) Inline with the guidance in Regulatory Guide 1.183 (Ref. 1,Appendix B,Sec. 5.3, Footnote 3), Entergy commits to implement the provisions of Sec. 11.3.6.5 of NUMARC 93.0 (Ref. 21) to address the prompt closing of the secondary containment incase of afuel handling accident during refueling operations.

(h) Based on the conclusion discussed under Item (e)above, the CR TEDE dose documented in this calculation isbounding for any outside air flow that may be assumed to enter the CR. As such, this calculation will not be affected by the results of the up-coming CR inleakage testing mandated by NRC Generic letter 2003-01 (Ref. 3), and no revision will be necessary.

PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Document ID32-5052589-01 Based on the Altemative Source Term Methodology (2038 MWI)

AR EVA Prepared by: John N.Hamawi Page 12

3. DESIGN INPUT AND ASSUMPTIONS The design input employed inthe analysis, and the associated references, are summarized inTables 3.1 through 3.3. The majority of the information inTable 3.1 was extracted from Ref. 12; a copy of this reference appears inAttachment D.

Pertinent assumptions employed inthe analysis are as follows:

(a) The postulated FHA was assumed to take place at the very start of fuel movement [24 hrs after reactor shutdown (all rods in)].

(b) The accident was assumed to take place inthe reactor cavity. Afuel assembly dropped inthe spent fuel pool would result infewer fuel rods damaged due to the significantly smaller drop height [see Table 3.1, Footnote (b)].

(c) *The accident was assumed to involve the dropping of a GE-14 peak-powered assembly onto other GE-14 peak-powered assemblies. The fuel damage listed inTable 3.1 (Item #A6) isfor such a scenario.

(d) The reactor building was assumed to be open during the refueling operations, with the normal ventilation on, such that all releases to the environment would be via the Reactor Building vent. This isthe most restrictive scenario with respect to the radiological impact. Potential releases via the Truck Lock would lead to lower CR doses due to the lower atmospheric dispersion factor from the Truck Lock to the CR fresh air intake (see Table 3.3). Inaddition, potential leakage via the RB siding isvery unlikely inview of the structural design of the RB walls above the refuel level floor (columns of structural steel and 6' pre-cast concrete wall panels with structural steel bracing and caulking), and the recent improvements for leak-tightness (see Footnote 2 inSec. 2).

(e) The stand-by gas treatment system (SGTS) was assumed to be unavailable (hence, an RB vent release without filtration). Inaddition, no credit was taken for the control room High Efficiency Air Filtration System (CRHEAFS); the CR ventilation system was assumed to remain inthe normal operating mode for 30 days.

(f) Inline with Ref. 1(Appendix B,Sec. 4.1), the radioactive material that escapes the fuel pool was assumed to get released to the environment over a2-hour interval. Analytically, this was accomplished by assuming abuilding air exchange rate of 4air changes per hour. This air exchange rate leads to [1.0

-exp(-4*10/60)] =48.7 %of the airbome activity getting released within 10 minutes, 86.5 %within 30 min, 99.2 %within 1hour, and 99.97 %within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

(g) The control room operators were assumed to be located at the base of a hemispherical cloud having a volume equal to the free air volume of the control room. Finite-cloud correction to the submersion dose was based on a nuclide-specific model; the Murphy/Campe equation inReg.

Guide 1.183 (Sec. 4.2.7) is non-conservative since it is based on an unrealistically high gamma energy for this accident (0.733 MeV, from Ref. 8).

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 13 AR EVA Table 3.1 DESIGN INPUT - FUEL HANDLING ACCIDENT No. DESCRIPTION I VALUE REFERENCE A - Source Term_

Al Power level for DBA analysis 2038 MWt Ref. 12

[Includes 0.5 %measurement uncertainty]

A2 Number of assemblies in core 580 Ref. 12 A3 Number of fuel rods in GE-14 fuel (10xl0 assembly) 92 Ref. 12 A4 Assembly average operatng power level 3.514 MWt Calculated Assembly (2038 MWt /580 assemblies]

A5 Maximum allowed radial peaking factor 2.1 Ref. 12 A6 Number of damaged fuel rods as a result of FHA (GE-14, Ref 12

.10xlO fuel, inpeak-power assemblies)Ca) -_151_e_.

A7 Equivalent number of damaged peak assemblies, and 1.641 Calculated fractions thereof [1 51 rods 192 rods per assy.)

Power level associated with damaged rods in peak Calculated A8 assoemlies 12.11 MWt 13.514 MWt

1.641 assemblies assemblies ' 2.1 Peaking Factor]

Fuel rod gap fractions (AST Methodology) 1-131 0.08 A9 Kr-85 0.10 Ref. 1 Other noble gases 0.05 (Reg. Guide 1.183, Table 3)

Other halogens 0.05 Alkali metals (Cs and Rb) 0.12 A10 Radionuclide inventory within damaged fuel rods See Table 3.2 Al1 Decay time prior to postulated accident 24 hrs Assumed values (a) Item #A6: GE-14 (10xlO) fuel assemblies were loaded into the PNPS reactorcore during Reload 13 (Ref. 12). It is anticipated that all future reloads will use GE-14 fuel assemblies, as well.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MW!)

Prepared by. John N. Hamawi Document ID 32-5052589-01 Page 14 AREVA Table 3.1 (Continued)

DESIGN INPUT B - Atmospheric Release Resulting from Postulated FHA B1l Percent of damaged-fuel rod gap activity release 100 % Ref. 1,Appendix B B2 Depth of water above fuel in refuel cavit(b) ;- 23 ft Ref. 12 Noble gases 1 B3 Overall pool decontamination factor Halogens 200 Ref. 1,Appendix B Alkalis Infinite Halogen composition in airborne release Elemental 57%

_ (composition above pool) Organic % Ref. 1,Appendix B B5 Refueling level free air volume 7.OE+05 ft3 Ref. 12 B6 Reactor building configuration during refueling operations Open B7Potential leakage points (a) RB vent (via the normal ventilation system)

Bto the atmosphere t) (b)Truck Lock door (open containment)

B8 Release duration to atmosphere J 2 hrs Ref. 1,Appendix B C - Control Room Characteristics C1 Control room free air volume 34,280 ft3 Ref. 12 C2 Air flow into CR (from fresh air intake, and from surrounding 1000 and Assumed vaiues(

areas as a result of ingress, egress and leakage) 9000 csm Post accident activation the Control Room High Efficiency Air N C3 Filtration System (CRHEAFS) INot credited Assumption (b) Item #B2: The core isapproximately at El. 70 fi; the water level during refueling isat El. 116 ft. Afuel assembly dropped inthe spent fuel pool would result infewer fuel rods damaged due to the significantly smaller drop height (Ref. 12). The water depth inthe spent fuel pool isalso> 23 ft [see Attachment D,Table Note (b)J.

(c) Item #B6: Recent improvements to the building leak -tightness minimize RB siding leakage as apotential release pathway (Ref. 12). See Footnote 4in Sec. 2. Inaddition, releases via the main stack are feasible if the Standby Gas Treatment System (SGTS) isinitiated and functioning properly. However, credit for SGTS filtration and release to the environment, via the main stack as an elevated release, was not assumed in this analysis.

Unfiltered ground-level releases via the RB Vent produced the greatest radiological impact in the CR, at the EAB, and at the LPZ, without exceeding the regulatory dose limits.

(d) Item #C2: The CR air intake rate was assumed to be 1000 cdm (alow value), and 9000 cfm (ahigh value bounding the 7200 cfm listed in Ref. 12). The intent isto show that there islittle impact on the CR dose for any flow within this range.

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 15 AREVA Table 3.1 (Continued)

DESIGN INPUT No. DESCRIPTION I VALUE REFERENCE D - OtherVarlables D1 Atmospheric dispersion factors from release points to See Table 3.3 Ref. 9,Tables 7.1 and 7.5 locations of interest Control Room 0-720 hrs 3.5E-04 m3lsec Ref. 1,pg 1.1 83-18 EAB 0 -2 hr 3.5E-04 m3/sec D2 Breathing rates 0 -8 hrs 3.5E-04 mrnsec Ref. 1,pg 1.183-16 LPZ 8-24 hrs 1.8E-04 m3/sec 24 -720 hrs 2.3E-04 m3/sec 0 -24 hrs 1.0 D3 Control room occupancy factors 24 -96 hrs 0.6 Ref. 1,pg 1.183-18

._ . _ . _96 -720 hrs 0.4 Control room 30 days Ref. 1,Secs. 4.1.3, 4.1.5 and D4 Exposure Intervals(e) EAB 2 hrs 4.2.6 LPZ 30 days Control room Contol TEDE TDE rom 5 rem 5rem Ref.

Ref. 1, 16,pgSec.

1.183-19, (b)(2)(iiii)and DSRegulatory dose limits EAB TEDE 6.3 rem Ref. 1,Table 6

_ LPZ TEDE 6.3 rem . __

(e) Item #D4: Even though all radioactivity isreleased to the atmosphere within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following a design-basis FHA, the exposure intervals for the CR personnel and receptors at the LPZ were assumed to be 30 days. This provides adequate time for cleanup of the airborne radioactivity still present within the CR after termination of the 2-hr release, and also accounts for the delayed release of noble-gas decay products from the refueling cavity water produced upon decay of halogens retained therein.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 16 AR EVA Table 3.2 PNPS Bounding, Undecayed Core Inventories for Halogens and Noble Gases Important In Radiological Evaluations

[From Ref. 5,Table 2.4]

Hal ens Noble Gases Radionuclide Inventory (Ci) Radionuclide Inventory (Ci)

BR 82 6.872E+05 KR 83M 8.638E+06 BR 82M 2.656E+05 KR 85 1.439E+06 BR 83 8.640E+06 KR 85M 1.979E+07 BR 84 1.593E+07 KR 87 3.956E+07 BR 84M 4.468E+05 KR 88 5.592E+07 BR 85 1.957E+07 KR 89 7.054E+07 BR 86 1.466E+07 KR 90 7.004E+07 BR 87 3.339E+07 XE131M 6.412E+05 BR 88 3.803E+07 XE133 1.150E+08 1128 1.919E+06 XE133M 3.541 E+06 1129 6.033E+OO XE135 5.869E+07 1130 4.655E+06 XE135M 2.297E+07 1130M 1.818E+06 XE137 1.012E+08 1131 5.71 6E+07 XE138 1.022E+08 1132 8.113E+07 XE139 8.237E+07 1133 1.1 50E+08 1134 1.284E+08 __

1134M 1.371E+07 1135 1.071E+08 1136 5.198E+07 1136M 3.179E+07 Notes (a) These inventories are bounding (individually for each radionuclide) for the following core parameters.

Power level: 2038 MWt Fuel enrichment: 3.9 - 4.6 w/. U-235 Core loading: 101.8 - 105.56 MTU (metric tons of uranium)

Bumup: 5 -60 GWD/MTU (b) The maximum bumup at the end of Cycle 15 ispredicted to be 51.7 GWD/MTU [19). Therefore, the condition of Footnote 11 of Reg. Guide 1.183 (Ref. 1,page 1.183-14] ismet and the fractions given inRegulatory Guide 1.183, Table 3,apply.

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID 32-5052589-01 Page 17 AREVA Table 3.3 Atmospheric Dispersion Factors for the Postulated FHA

[From Ref. 9,Table 7.1 and 7.5]

No. Release Point Receptor Point Interval Concentr. 3(X/Q) Gamma (XIQP)3

_ ___ _ __ _ __ _(sec/m ) _ _ (sec/rn )

1 EAB (actual) Ca) 0- 2 hrs 7.479E-04 3.199E-04 0- 2hrs 3.692E-05 3.551 E-05 2 - 8hrs 1.915E-05 1.782E-05 2 LPZ (4.25 miles) 8 -24 hrs 1.066E-05 9.627E-06 24 - 96 hrs 4.339E-06 3.745E-06 Reactor building vent 96 -720 hrs 1.194E-06 9.656E-07 0-2 hrs 1.76E-03 2 -8 hrs 1.25E-03 3 ~~~~~Control Room 8-2 r .6-4W Fresh Air Intake 8 -24 hrs 4.26E-04 N/A 24 -96 hrs 3.67E-04 96 - 720 hrs 3.15E-04 4 EAB (actual) 0 -2 hrs See RB vent'c 5 LPZ (4.25 miles) 0-720 hrs 0-2hrs 9.72E-04 Truck Lock door 2- 8 hrs 7.52E-04 6 ~~~~~Control Room 8-2 r .0-4W 6 Fresh Air Intake 8-24 hrs 2.80E-04 N/A 24 - 96 hrs 1.93E-04

_ 96 -720 hrs 1.61E-04 (a) The EAB distances employed inthe atmospheric dispersion analysis are from the closest point of the reactor building; as such, they conservatively apply to releases via the RB vent, which isat the plant SW comer. The critical receptor isinthe true NE sector, at a distance of 486 m(at the over-water exclusion zone).

(b) See Attachment Afor definition of the gamma ( IQ). The gamma (Q/Q) isenergy dependent, and decreases with increasing energy for ground-level releases. The listed gamma (X/Q)s were conservatively based on Xe-133 (which emits low-energy gammas).

(c) The atmospheric dispersion factors for releases via the Truck Lock (which isin the plant W side, near the NW comer of the building she), are conservatively bounded by releases from the reactor building proper.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

A R E VA Prepared by. John N.Hamawi Page 18

4. ANALYSIS AND RESULTS The accident scenario is summarized in Sec. 2. Please refer to that section for details.

4.1 Source Term Computation of the halogens and noble gases released from the fuel rods postulated to get damaged as a result of the accident is summarized in Table 4.1. The following are noted:

(a) The activity listed in Table 4.1 is undecayed. The pre-accident decay correction is handled automatically by ELISA-2, based on a user-specified value for decay time3.

(b) The pool decontamination factor for halogen retention is handled separately by ELISA-2. Exclusion of the DF from the source term permits ELISA-2 to properly account for the generation of noble-gases by the halogens retained by the pool water.

(c) The postulatedfuel damage is 151 fuel rods out in GE-14 fuel assemblies. The corresponding damage expressed in assemblies is 1.641 (from Table 3.1, Item A7),

3 See Appendix B,ELISA-2 Run Case #A,output page 9for the decay-corrected activity.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Harnawi Document ID32-5052589-01 Page 19 AR EVA Table 4.1 Radionuclide Source Term Halogens and Noble Gases Important In Radiological Evaluations Undecayed Inventory (Ci) Fuel Rod FHA Undecayed Radionuclide Full Core P Gap Fraction Source Term (From Table 3.2) Peak Assembly (From Table 3.1) (Ci)

BR 82 6.872E+05 2.488E+03(a) 0.05 2.042E+02(b)

BR 82M 2.656E+05 9.617E+02 0.05 7.892E+01 BR 83 8.640E+06 3.128E+04 0.05 2.567E+03 BR 84 1.593E+07 5.768E+04 0.05 4.733E+03 BR 84M 4.468E+05 1.618E+03 0.05 1.328E+02 BR 85 1.957E+07 7.086E+04 0.05 5.815E+03 BR 86 1.466E+07 *5.308E+04 0.05 4.356E+03 BR 87 3.339E+07 1.209E+05 0.05 9.921 E+03 BRE8 3.803E+07 1.377E+05 0.05 1.130E+04 . .

1128 1.919E+06 6.948E+03 0.05 5.702E+02 1129 6.033E+00 2.184E-02 0.05 1.793E-03 1130 4.655E+06 1.685E+04 0.05 1.383E+03 1130M 1.818E+06 6.582E+03 0.05 5.402E+02 1131 5.716E+07 2.070E+05 0.08 2.717E+04 1132 8.113E+07 2.937E+05 0.05 2.411 E+04 1133 1.150E+08 4.164E+05 0.05 3.417E+04 1134 1.284E+08 4.649E+05 0.05 3.815E+04 1134M 1.371 E+07 4.964E+04 0.05 4.074E+03 1135 1.071 E+08 3.878E+05 0.05 3.182E+04 1136 5.198E+07 1.882E+05 0.05 1.544E+04 1136M 3.179E+07 1.151E+05 0.05 9.446E+03 KR 83M 8.638E+06 3.128E+04 0.05 2.567E+03 KR 85 1.439E+06 5.21 OE+03 0.1 8.551 E+02 KR 85M 1.979E+07 7.165E+04 0.05 5.880E+03 KR 87 3.956E+07 1.432E+05 0.05 1.175E+04 KR 88 5.592E+07 2.025E+05 0.05 1.662E+04 KR 89 7.054E+07 2.554E+05 0.05 2.096E+04 KR 90 7.004E+07 2.536E+05 0.05 2.081 E+04 XE131M 6.412E+05 2.322E+03 0.05 1.905E+02 XE133 1.150E+08 4.164E+05 0.05 3.417E+04 XE133M 3.541 E+06 1.282E+04 0.05 1.052E+03 XE135 5.869E+07 2.125E+05 0.05 1.744E+04 XE135M 2.297E+07 8.317E+04 0.05 6.825E+03 XE137 1.012E+08 3.664E+05 0.05 3.007E+04 XE138 1.022E+08 3.700E+05 0.05 3.037E+04 XE139 8.237E+07 2.982E+05 0.05 2.447E+04 (a) = [6.872E+05 (core Ci) I 580 (assemblies) ] ' 2.1 (peaking factor)

(b) = 2.488E+03 (peak assembly Ci)

0.05 (gap fraction)

1.641 (ruptured assemblies, from Table 3.1)

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 20 AR EVA 4.3 Results The design input inSec. 3,along with the source term in Sec. 4.1, were provided as input to ELISA-2 for computation of the FHA radiological impact. The results are presented inTable 4.2.

The following are noted:

(a) The thyroid and skin doses presented inthis table are for informational purposes only. The AST methodology provides regulatory dose limits only for the TEDE (b) Refer to the computer outputs in Attachment Efor complete details (including dose rates, interval doses and cumulative doses to other organs and air).

(c) Refer to Attachment A for an alternative (non-safety-related) analysis based on RADTRAD.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handiing Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 21 AR EVA Table 42 Fuel Handling Accident Radiological Impact Outside TEDE Whole Thyroid Skin Dose ELISA-2 LOCATION Exposure Air Intake Dose Body Dose (P + y) Run Case Interval Rate ( (rem) (rem) (rem) Reference 28691.32 2.059 Case #A, Control 1000 cfm 2.846 0.0455 [99.95 [97.25] #A 26se Rontom 30 days Cas26A Roo9000 cfm 2.863 0.0527 91.63 2.164 Case #A, 90Cfn [98.16] 0(52 99.94] [96.99] Ouptg 143 39.17 1.125 Outpu pg, EAB 2 hrs N/A [82.96] 0.245 [99.38] f[73.63] 17.

LPZ '30 days N/A NA 0.0920

[64.12] 0.0330 1.954

[.33 98.33] 0.0836

[52.54] Case17puP Notes:

(a) Shown in square brackets are the following:

The percent contributions to the TEDE and thyroid doses via the inhalation pathway

The percent contributions to the skin dose by beta radiation (b) The whole body values have been calculated, and are for external radiation. Asample calculation follows, for the EAB:

Whole body dose = 1.439 (rem TEDE) (100 -82.96) / 100 = 0.2452 rem (c) The thyroid dose includes both the inhalation and external radiation pathways.

ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Altemative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 22 References

1. USNRC Regulatory Guide 1.183, "Alternative Radiological Source Terms For Evaluating Design Basis Accidents at Nuclear Power Plants," July 2000.

2. J. DiNunno, F.Anderson, R.Baker and R.Waterfield, 'Calculation of Distance Factors for Power and Test Reactor Sites,' AEC, Division of Licensing and Regulation, TID-14844 (March 1962)

3. NRC Generic Letter 2003-01, Control Room Habitability' (6/12/2003)

4. AREVA Framatome ANP Proposal Number EPRG-04-1329.0, Rev. 0,addressed to Entergy Nuclear Northeast, Pilgrim Nuclear Power Station, "Update FHA" (913012004)

5. AREVA Framatome ANP Calculation 32-5046797-00, 'Pilgrim - Bounding LOCA Source Terms for Design-Basis Applications at 2038 MWtf, J. N.Hamawi (September 2004)

6. J.N.Hamawi, 'ELISA-2 -A Software Package for the Radiological Evaluation of Licensing and Severe Accidents at Light-Water Nuclear Power Plants Based on the Classical and Afternative-Source-Term Methodologies," ENTECH Engineering, Inc., Technical Document P100-R22 (Vols. A-G, Version 2.2, May 2002) [CSI Version 2.2, Records Center File No. 2A4-Elisa2-2.2-SRN]

7. NUREG/CR-6604, -RADTRAD: A Simplified Model For RADionuclide Transport and Removal And Dose Estimation,' December 1997, and Supplements (Supp. 1,6/1999, and Supp. 2 10/2002)

8. K.G.Murphy and K.M.Campe, 'Nuclear Power Plant Control Room Ventilation system Design for Meeting General Criterion 19,' 13th AEC Air Cleaning Conference (1974)

9. AREVA Framatome ANP Calculation 32-5052821-00, 'Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg. Guide 1.145 and 1.194 Methodologies,' T. A. Messier (November 2004)

10. U.S. Nuclear Regulatory Commission Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants", June 2003.

11. J. N.Hamawi 'AEOLUS AComputer Code for the Determination of Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents During Continuous, Intermittent and Accident Conditions in Open-Terrain Sites, Coastal Sites and Deep River Valleys', ENTECH Engineering, Inc. (Vols. A-E, December 1995) [CSI Version 1.0, Records Center File No. 1123-00-3005.03-243]

12. Entergy letter NESG 04-097, addressed to R.J. Cacciapouti (FANP, Manager, Nuclear & Radiation Engineering), from F.J. Mogolesko (PNPS, Sr. Project Manager), dealing with design input for the radiological analysis of a design-basis fuel handling accident at the Pilgrim Station (10/27/2004)

13. EPA 520/1-88-020, Federal Guidance Report No. 11, 'Limiting Values of Radionuclide Intake and Air Concentration, and Dose Conversion Factors for Inhalation, Submersion, and Ingestion' (ORNL, September 1988)

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Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 23

14. EPA 402-R-93-081, Federal Guidance Report No. 12, 'External Exposure to Radionuclides inAir, Water, and Soil' (ORNL, September 1993)

15. USNRC, NUREG-0800, Standard Review Plan 6.4, 'Control Room Habitability System,' Rev. 2,July 1981

16. Code of Federal Regulations Title 10 Part 50.67 (IOCFR50.67).

17. D.H.Slade (Ed.), "Meteorology and Atomic Energy- 1968,' USAEC, TID-24190 (1968)

18. NRC Regulatory Guide 1.109, 'Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CRF Part 50, Appendix I,' (Rev. 1,10/1977)

19. PNPS Nuclear Change ER # 03120058, 'Re-Seal Joints in Pre-Cast Panels' (2004) [See also Maintenance Request MR04107653, implemented inOctober 2004.)

20. J.V. Ramsdell and C.A. Simonen, 'Atmospheric Relative Concentrations inBuilding Wakes,'

NUREG/CR-6331, Rev. 1 (ARCON-96, May 1997)

21. NUMARC 93-01, 'Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants'

22. USNRC Regulatory Guide 1.25 (Safety Guide 25), "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident inthe Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors,' March 12, 1972.

23. US Regulatory Guide 1.145, Rev. 1,Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (Nov. 1982)

See Attachment Afor a copy of this reference, or excerpts thereof.

ABasedA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the AHemative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 24 ATTACHMENT A ALTERNATIVE FHA ANALYSIS BASED ON RADTRAD This attachment presents the result of the FHA radiological impact evaluated through use of the NRC RADTRAD computer code, and comparison of the results with ELISA-2. It is emphasized that RADTRAD is not currently in the FANP Computer Software Index, and as such it cannot be used for safety-related calculations at FANP. The RADTRAD analysis isprovided for informational purposes only.

The design input employed in RADTRAD is as given in Secs. 3 and 4.1 in the main body of the calculation. The RADTRAD results for the scenario with 9000 cfm air intake into the CR, and for the offsHe receptors, are presented in Table A.1. This table also shows the comparison between the RADTRAD and ELISA-2 results. In general, there is good agreement between the two computer codes, with ELISA-2 predicting higher FHA doses in the analyzed scenarios for the following reasons:

(a) ELISA-2 has a more extensive list of halogens and noble gases in Rts data library (see Table 4.1).

(b) ELISA-2 accounts for the release of noble-gas decay products from the refueling-cavity as a result of the decay of halogens retained by the water,.

(c) In ELISA-2, the finite-cloud correction factor for submersion in the control room contaminated air is nuclide specific, based on the actual energy spectrum associated with the photon radiation emitted by each radionuclide [the Murphy/Campe equation in Reg. Guide 1.183 (Sec. 4.2.7) is non-conservative since it is based on an unrealistically high gamma energy for this accident (0.733 MeV, from Ref. 8)]. See ELISA-2 Run Case #A, output page 10 for a comparison of the finite-cloud correction factors in the present application; they range from 0.0221 for Br-84 to 0.978 for Kr-83m in ELISA-2, whereas the Murphy/Campe value is 0.0291. For the two important radionuclides, 1-131 and Xe-133, the factors are 0.0281 and 0.0488, respectively.

Inthe present application, the CR TEDE doses are controlled by the inhalation pathway and the iodines, and as a result, the doses predicted by the two codes are very close (within 5.7 %). At the LPZ, on the other hand, the external radiation contribution (from both halogens and noble gases) becomes more significant, and leads to a higher difference between the two codes (11.2 %/6). The whole body dose at the EAB is under-predicted by RADTRAD by as much as 21.5 %,due primarily to the short list of radionuclides in RADTRAD. The thyroid doses are within about 5 %for the CR, and 0.1 % at the offsite receptors.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 25 AREVA Table A.1 Comparison of the RADTRAD and ELISA-2 Doses for the PNPS Design Basis FHA

[From Table 4.2 for the ELISA-2 results, and from pg. 139 for the RADTRAD results]

LOCATION Software TEDE Dose Whole Body Thyroid Dose

. (rem) (rem) (rem)

ELISA-2 2.863 0.0527 91.58(a) goo cfm) RADTRAD 2.696 0.0291 86.99 Differencesb 6.83 % 44.8 % 5.01 %

ELISA-2 (with concentration 1.439 0.245 38.93

& gamma X/Q) .

ELISA-2 EAB (with concentration 1.767") 0.5728(e) 38.93(")

x/Q only)

RADTRAD 1.643.. 0.4499 38.90 Difference 7.02 % 21.5 % 0.08 %

ELISA-2 (with concentration 0.0920 0.0330 1.921

& gamma xIQ)

ELISA-2 LPZ (with concentration 0 . 0 9 33 (9) 0.03430 1.921(s) x/Q only)

RADTRAD 0.0811 0.0222 1.920 Difference 13.1 % 35.3 % 0.05 %

(a) 91 .63 (rem)' 0.9994 = 91.58 rem (from Table 4.2)

(b) Defined as 100 * (ELISA RADTRAD) / ELISA-2 (c) = 0.245 rem * (7.479E-04 /3.199E-04) (concentration to gamma X/O ratio, from Table 3.3)

(d) = (1.439 - 0.245) inhalation pathway + 0.5728 external radiation (e) Same as in previous row, since it is actually based on the concetration (X/Q)

(f) = 0.0330 rem * (3.692E-05 /3.551 E-05) (concentration to gamma X/Q ratio, from Table 3.3)

(f) = (0.0920 - 0.0330) inhalation pathway + 0.0343 external radiation

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R EVA Prepared by. John N.Hamawi Page 26 A7TACHMENT B The Finite-Cloud Gamma (XlO)

As pointed out inthe main body of this report, the analytical models in ELISA make use of two dispersion parameters:

(a) The concentration (X/Q), or (xlQ):, which is used for the determination of airborne concentrations at offsite receptors of interest and the ensuing radiation doses due to immersion in semi-infinite clouds, and (b) The gamma (XIQ), or (X/Q)g, which is employed for the computation of external gamma radiation doses due to immersion infinite clouds of radioactive material.

The manner inwhich these parameters are applied inthe assessment of offsite radiological impacts ispresented below for additional clarification.

By definition, the (XIQ)c isa measure of the ground-level relative airborne concentration of released radioactivity at a given distance from the source. That is,if the release rate is defined as Q', then the airborne concentration at the receptor of interest is:

Xi = 01' (X/Q)c (1) where Xi = airborne concentration of radionuclide i (pCUM 3)

= radionuclide release rate to atmosphere (pCiisec)

(xIQ)c = concentration dispersion factor (sec/r).

Exposure to this concentration could result in both inhalation and external radiation doses. Ifconsideration is given to a number of released radionuclides, the basic equation for the Committed Effective Dose Equivalent (CEDE) due to inhalation has the form:

OcEDE' (XIQ)c B Qi' (DCFI)i (2) where DCEDE' = CEDE dose rate (mrem/hr),

B = individual breathing rate (m3lhr), and (DCFI)i = CEDE dose conversion factor due to inhalation, for nuclide i (mrem per PCi inhaled).

With respect to the computation of the Deep-Dose Equivalent (DDE) from airborne external gamma radiation, two models may be employed:

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Altemative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R EVA Prepared by. John N.Hamawi Page 27 (a) The semi-infinite cloud model, which is conservatively applicable only for ground-level releases (asimplistic model based on the assumption that the airborne concentration at the receptor of interest is the same everywhere), and (b) The finite-cloud model, which takes into consideration the actual plume dimensions, elevation above the receptor, and gamma radiation spectra.

For the semi-infinite cloud model, the applicable equation for the DDE is as follows:

DNDE' = (X/Q)c Qi' (DCFE)i (semi-infinite cloud) (3) where DDDE' = DDE dose rate (mremlhr),

(DCFE)i = DDE dose conversion factor due to external radiation, for radionuclide I (mrem-m 3lhr-

buci), - -

and the other parameters are as previously defined. The model has two drawbacks:

Itcould be overly conservative for receptors close to the release point (for ground-level releases under stable conditions with limited plume dispersion), due to the fact that the high concentration at the receptor location isassumed to exist everywhere, and

It is not suitable for elevated plumes since gamma radiation emanating from the plume could reach a receptor on the ground even though the plume itself is still aloft [i.e., even though the concentration (O/Q) at ground level could be equal to zero].

Inthe models that deal with the determination of external gamma dose from finite plumes, the equations contain complex integrals representing the spatial distribution of the radioactivity inthe plume and the transmission of radiation through air. The desire to have one form of equation which would apply for both finite and semi-finite cloud models, has prompted the definition by the author of the 'gamma (x/Q)', as described indetail in Ref. 11.

Indeed, through use of this parameter, the finite cloud DDE dose rate equation takes the form:

DDDE' = (X/O), z Q0 (DCFE)i (finite cloud) (4)

The form of this equation is identical to Eq. (3)for the semi-infinite cloud, the only difference being the replacement of the concentration (x/Q) by the gamma (X/Q). Thus, physically speaking, the gamma (XIQ) for a given finite cloud is numerically equivalent to the relative concentration of a semi-infinite cloud which will yield the same gamma radiation dose as the finite cloud. Indeed, at distant receptors, where the plume dimensions approach limiting conditions, the gamma (X/Q) equations reduce to those for the concentration (XIQ).

Note that the finite-cloud equation applies for both ground-level and elevated releases, and that the gamma radiation spectrum associated with the airborne radioactivity is properly accounted for by the gamma (X/Q).

Also, the concentration (X/Q)s and the gamma (XIQ)s inthe above equations represent either plume centerline

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID 32-5052589-01 Page 28 AR EVA or sector-average values, the former being for estimating short-term dispersion effects, and the latter for or sector-average values, the former being for estimating short-term dispersion effects, and the [after for dispersion during relatively longer periods of time.

From Ref. 11, the gamma (X/Q) equations are as follows:

(XIQ)g = 2 Pa (h1 +K 12) I(ITu) (plume centerline model) (5) and (XIQ)g = 2 Pa (11 + K 12) / [X U (T/8)] (sector-average model) (6)

Inthese equations:

p = linear attenuation coefficient for air at agiven gamma energy (1r/m),

Pa = linear energy absorption coefficient for air at a given energy (1/m),

K - buildup factor for air, defined as (Ref. 21, Sec. 7.5.1):

K = (P - Pa) / la, U = prevailing wind speed (m/sec),

x = downwind distance (m), and (Tr/8) = angular width of a 22.5-degree sector.

Parameters Ix,(2, 11and 12 are the results of numerical integrations accounting for dispersion of the effluent plume, and are functions of the plume standard deviations, plume elevation, and photon energy. See to Ref. 17 (Sec. 7.5) for further details. Software for their computation is available (Ref. 11 for both the plume centerline and sector average models, and Ref. 18, Appendix F,for the sector-average model). I general, a conservative radionuclide or gamma energy can be selected to accommodate multi-energy spectra and their variation with time.

A A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R EVA Prepared by: John N.Hamawi Page 29 ATTACHMENT C ELISA-2 FEATURES AT A GLANCE ELISA-2 is a software package for the radiological Evaluation of Llcensing and Severe Accidents at nuclear power plants. It is based on deterministic models for the computation of radioactivity levels, gamma spectra and radiation exposures following routine and accidental releases of fission products, activation products and actinides. ELISA-2 is suitable for the radiological evaluation of practically all postulated design-basis accidents at light-water nuclear power plants (PWRs and BWRs). It is also suitable for selected scenarios involving routine releases. Briefly, the basic features of the software include the following:

Release types:

1. Classical accidental releases (instantaneous releases from the source/core at the time of the accident),

2. AlternativW-Source-Term (AST, NUREG-1465, Reg. Guide 1.183) accidental releases (gradual, time-phased releases from the source),

3. Routine releases (air submersion, inhalation and ground-shine pathways only), and

4. Pre-accident constant-feed conditions (time-interval dependent), followed by accidental releases (such as gaseous-tank fill ups prior to rupture, and establishment of reactor coolant equilibrium conditions prior to a line break and iodine spiking).

One-, two- and three-member decay chains, and second parents; materially-balanced equations without black-hole sinks (such that, for instance, halogen decay inthe core and inany other place of accumulation, leads to the production of airborne noble gases).

414 radionuclides; up to 12 user-specified element groups; instantaneous or multi-phase releases from the source, with pre-release buildup and decay; three chemical forms for each element group.

One- and two-compartment spray models, optionally with user-specified DFs for automatic spray-effectiveness termination; time-dependent spray removal constants for each element group and each species; time-phased releases from the source, split between the sprayed and unsprayed regions according to user specification; time-dependent air circulation flow between sprayed and unsprayed regions.

Pre-accident source inventory decay (as needed for fuel handling accidents, for instance).

Time-dependent compartment filtration flows; intake, recirculation and exhaust filter time-dependent bypass fractions; filter removal efficiencies for each element group and each species.

Time-dependent radioactivity levels at all places of accumulation, including ground contamination.

Time-dependent release rates, interval releases and cumulative releases to the atmosphere; released cloud concentrations.

ABased A R E VA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 30

In-transit buildup and decay for offsite receptors.

Time-dependent radiation dose rates, interval doses and cumulative doses [nuclide-specific, group-element specific and overall totals; inhalation, air submersion, ground contamination; air gamma, air beta, skin, 7 organs, Effective Dose Equivalent (EDE), classical TI D-1 4844 thyroid for iodines, Regulatory Guide 1.109 whole body; percent contributions of betas to skin dose; percent contribution of inhalation pathway to total doses to the lung, thyroid and EDE; partial occupancy adjustments for CR personnel].

Time-dependent and time-integrated gamma spectra wherever radioactivity accumulates and in the released radioactive cloud (ORIGEN-2 18-group and user-specified reduced spectra; user-specified element groups, and all groups combined); preparation of output files with spectral information for input into shielding codes. (Examples of spectral files and uses: RCS liquids and EQ/accessibility applications; filter radioactivity and CR habitability/filter heat-up rates; containment airborne radioactivity and direct-shine doses/process-monitor readings; overhead

..cloud radioactivity and CR doses.)

Finite-cloud adjustments for air submersion exposures (compartments and offsite receptors, the latter requiring as input special finite-cloud-corrected atmospheric dispersion factors).

Data library based on ORIGEN-2 (decay constants, branching fractions, photon spectra) and Federal Guidance Reports 11 and 12 (EPA 520/1-88-020 and EPA 402-R-93-081, dose conversion factors); software-prepared tabulation of the data library with identification of missing information.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Document ID 32-5052589-01 Page 31 AREVA ATTACHMENT D COPIES OF SELECTED REFERENCES Included inthis attachment isa copy of the following reference:

12. Entergy letter NESG 04-097, addressed to R.J. Cacciapouti (FANP, Manager, Nuclear &Radiation Engineering), from F.J. Mogolesko (PNPS, Sr. Project Manager), dealing with design input for the radiological analysis of a design-basis fuel handling accident at the Pilgrim Station (10/27/2004)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Document ID32-5052589-01 Page 32 AREVA Reference 12

E75 IEntergy y Nudear Generation Company En t y TV Pilgrym Nuclear Power S0a26 GOO Rocky Kilt Rosad Plymou~th. MA 02360 on October 27, 2004 NESG 04-097 Richard J. Cacciapouti Manager, Nuclear & Radiation Engineering Framatome ANP, Inc.

400 Donald Lynch Boulevard Marlborough, MA 01752

Dear Mr. Cacciapouti:

The following information is to be used by Framatome ANP in support of Pilgrim Station Fuel Handling Accident calculations. See Attachment 1 below.

My only concern with these design inputs is that physical lengths are expressed in feet and meters. This is due to the reference documents that support the values. Having a mixture of units is a potential error trap. I caution you and your staff to be highly sensitized to this observation.

Should you have any questions, please call me directly at 508-830-7832.

Sincerely Yours, Dr. Fred J. Mogolesko Senior Project Manager Attachment FJM:jmp

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 33 ARE VA Entergy Attachment 1 PNPS AST - FHA - DESIGN INPUT No. DESCRIPTION V VALUE REFERENCE A - Source Term Al Power level for DBA analysis 2038 MWt Ref. 1A

_ [lncludes 0.5 %measurement uncertainty2 A2 Number of assemblies incore 580 Ref. 1D A3 Number of fuel rods in GE-14 fuel (10xlO assembly) 92 Ref. 2 A4 Maximum allowed radial peaking factor 2.1 Ref. 2 A5 Number of damaged fuel rods as a result of FHA (GE-14, 151 Ref. 2 1Oxl0 fuel, in peak-power assemblies)(al A6 Predicted maximum bumup at end of Cycle 15 51.7 GWDIMTU Ref. 3 A7 Undecayed core inventory See Ref. 11 Ref. 11, Table 2.4 B - Refueling Level Characteristics B1 Depth of water above fuel in refueling cavitym) ;b23 ft Ref. 4 B2 Refueling level free air volume 7.OE+05 ft3 Ref. 5 (pg 14)

B3 Standby gas treatment system iodine filtration efficiency (all 99 % Refs. 1B and 10 species), for main slack releases Rebuerng bvel leak tightness has been recently improved. Maintenance Request MRD4 107653 was implemenled hIOctober 204 lo reseal the Joints In ve reactor bulkding pre-cast panels. ThIs MRwas compeited under Nuclear Change ER03121X)S8 Reseal Joints InPre-Cast Panels.

This design change wil allow for the re-sealng of the esterior horIzontal and vertical B4 Refuering level leak lightness Joints inhe pmecast panels of the Reactor 8uilsrq trorm te refuel loorelevation I1T-

.~ :iet

.. sep oi he pan satelevation 165-

.11 . The materials chosenlortthe sealant and bacidng rod are sknlar to te edsting materials. The installation rnethods used wil ensure that the material Isproperly Instaled boprovide leak-ight joints. This wilt he!p maintain secondary containrnent integrity.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 34 AR EVA E-ntergy Attachment 1 Page 2 C - Control Room Characteristics Control room 34 280 ft3 Ref. 6A Net volume of normal Cable spreading room, computer 28,620 f Ref. 6B ventilation envelope room, storage room. and corridor Total 62.900 fl3 Calculated, with rbund-off Normal intake 14,000 cfm During nortn31 opeation, the MCRECS provides heating, ventilaton ard air ondiftxig to the CREon EL37. and the CSR and Cormputer Room on EL 23. The MCRECS consists of two NVAC trains.

each rated to deliver 100% of design low, heating and corilrng to te CRE. CSR and Computsr Roorn. Each train contains a rorninal 14,000o dm supply fan (VAC.

104AG), a nominal 12.000 drn return fan (VRF-101A), a 48.000 Btu/hr Ventilation flow for entire refrigeration unit (VRC-101AJB) and a C2 volume of normal 9900 so Btu0br heater. The d; erence ventilation envelope Ingress/egress 9 cfm between supply and rercuation Dow rates pressuizes the MICR rclathve to afpining spaces. The supply ans draw a rmiure of outside asplus the discharge ol the tedroulatn tans during norrnal operation.

An erromnozer controls danpers to adiust the ratio of fresh to redrculated air flows for an energy efrcenntoperation. PNPS Design Basis Program; Topical Design Basis Docurnent -110: Control Roorn Reference 7 The ctual flow fates measured during the C3 Normal ventilation flow supplied to the CR -6,700 cfm last MCRECS certified air babnce.

Reference 7 Additional inflow into CR from surrounding ventitation zones 500 chit Assumed value during normal-ventilation configurationc5)

C5te) Post accident activation time of the Control Room High 30 mi Assumed value Efficiency Air Filtration Sy tem (CRHEAFS) 30miAsuedvau 0 - 0.5 hrs and 0.5 - 720 hrs Unfiltered -7200 cim Sum of entries in #C3 and #C4 C6"' Post accident CR air w/o CRHEAFS inflow 0.5 - 720 hts Unfiltered 10 cfm Ref. 8, Ingresslegress with CRHEAFS 500 cfm Assumed inleakage Fltered 1100 cfm Ref. IC, and Ref. 9, pg 12 0 C7(c) Control room charcoal filtration iodine removal efficiency 95% R IC 01 C7"' (all species) 95 %_Ref._1_C 1

I

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-1 A R E VA Prepared by: John N. Hamawi Page 35 Entegy Attachment 1 Page 3 Table Notes:

(a) Item #AS: GE-14 (10x1O) fuel assemblies were loaded into the PNPS reactor core during Reload 13 (Ref. 2). It is anticipated that all future reloads will use GE-14 fuel assemblies, as well.

(b) Item #11: The core is approximately at El. 70 ft; the water level during refueling is at El. 116 ft. Fuel in the reactor basin is covered by 46 feet of water during fuel handling operations. A fuel assembly dropped inthe spent fuel pool would result in fewer fuel rods damaged due to the significantly smaller drop height (Re!. 4).

The floor of the spent fuel pool Is at El 78.25 feel (Reference 4). A fuel storage rack is 165.375 Inches high with a 6.25 inch plenum below R. Fuel rack height is 165.375+625+1.0 for material dimensions, or 172.625 inches or 14.39 feet. Normal water level is El 116-78.25-14.39-23.36 feet of water above fuel.

(c) Use of CRHEAFS is only on a need basis to meet the CR regulatory dose limit.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 36 REFERENCES

1. PNPS Technical Specifications A. Amendment 201, "1.0 Definitions - Design Power."

B. 3.7.B.1 "SGTS" C. 3.7.B.2 "CHREAFS" D. Pilgrim Station PDC 03-01 dated 3/21/2003

2. Office Memorandum Dept. Doc. OSD 00-088, ODesign Criteria Input Request for Cycle 14 Reload Core Design Change, PDC 01.03," from S. Paranjape - Attachment 1 (2 pages).

3. Memorandum from S. Paranjape to P. Compagnone, August 12, 2003 - Attachment 2 (1 page).

4. Drawing M23, Equipment Location Sections DD &LL, Rev. E8. Holtec: HI-92925- PNPS Spent Fuel Storage Capacity Expansion for Fuel Rack Dimensions

5. Calculation PNP-q-1-ERHS-X.G4-127, uEnvironminprtal Qualificatin.-, Airborne Rhdi1!ion Levels in the Reato, Building Secondary Contai.nment," Revision 0.

6A. Calculation C15.0.3411, "Control Room Volume," Revision 0.

6B. Calculation PNPS-1-ERHS-XI.L28, Rev. 0, CR Habitability Radiological Reassessment for DBA LOCA.

7. -M48A, Specification for Air Conditioning Units, Rev. 1, 5/26/1969

- M51, Centrifugal Fans, Rev. 7,2/18/1971

-M286, Heating & Ventilation & Air Conditioning Temperature Control Diagram for Control Room Cable Spreading & Computer Room, Rev. Ell, 4/1/2001

-M292, Control & Cable Spreading Room, Intake Structure & Access Control Warehouse &

Machine Shop, Air Flow Diagrams, Rev. E24, 3/11/2001

-SG90-600, Control Room Heating Ventilating & Air Conditioning HVAC Air Balance Final Report, 7/17/1990

8. USNRC, NUREG-0800, Standard Review Plan 6.4, 'Control Room Habitability System,"

Rev. 2, July 1981

9. Procedure 2.2.46, "Control Room Cable Spreading Room, and Computer Room Heating, Ventilation, and Air Conditioning System," Revision 38.

10. Calculation S&SA 154, 'SGTS Train Efficiency For Radioiodine Removal by Dual Bank Carbon Adsorbers," Revision 0.

11. AREVA Framatome ANP Calculation 32-5046797-00, "Pilgrim - Bounding LOCA Source Terms for Design-Basis Applications at 2038 MWt", J. N.Hamawi (September 2004)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by. John N.Hamnawi Document ID32-5052589-01 Page 37 AR EVA

12. NEDE-32868P, Rev.1, Section 2.1.3, GE-14 Compliance with Amendment 22 of NEDE 24011 -P-A (GESTARII).

A A RE ABased VA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 38 ATTACHMENTE LIST OF COMPUTER RUNS Included inthis attachment are copies of the following computer runs associated with the present calculation:

ELISA-2 Case #A Fuel Handling Accident radiological evaluation, with two stacked cases:

CR with 1000 cfm outside air intake

CR with 9000 cfm outside air intake Case #B FHA - EAB doses (with finite-cloud gamma X/Q)

Case #C FHA -LPZ doses (with finite-cloud gamma XIQ)

RADTRAD Case #A FHA (CR with 9000 cfm outside air intake, EAB and LPZ)

The pages which follow include the input and/or output listings in the following order:

ELISA-2 Case #A Main Output File: Pages 39 - 78 Case #B Main Output File: Pages 79 - 96 Case #C Main Output File: Pages 97 - 114 RADTRAD Case #A Nuclide Inventory File: Pages 115 - 125 Release Fraction and Timing Fire: Pages 126 - 126 Main Output File: Pages 127 - 141 It isnoted that both ELISA-2 and RADTRAD main output files include the listings of the input files.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawl Document ID32-5052589-01 Page 39 AREVA ELISA-2 Run Case #A - Main Output File

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Tern Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 40 AR EVA 4##t### # tat allot

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ZNTZCR RNGINEERING, INC., WE8ITOROUCH, MA RELRAse VERSION/LEVEL.. t Verulon 2.2 RELEASE DATE .......... 1 May 23,2002 PROBLEM SUBMITTED ON .. : 28-Oct-04 1745s:33 INPUT FILE ............ 1 e1Laa2-FEA-CR. e1l DATA LIBRARY FILE ..... 1 /SCL/ellva2-2 .2/ellua2-2 . 1lb OUTPUT FILE ........... 1 elina2-FMA-CR.eI2 PROTON SPECTRA FILE l1 1 e1Lga2-FRA-CR. e13 PROTON SPZCTRA FILE t2 : e1Lsa2-?V1A-CR. e14

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID 32-5052589-01 Page 41 AR EVA BLISA-2 (LICENSING e STVERN ACCIDMNT RADIOLOGICAL EVALUATIONS - ZMCR MNO. - Rel. Verslon 2.2 May 23,20021 28-Oct-04 PAGC I INPUT DATA LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345678901234567890123456789012345679901234567890123456789012345678901234567890123456789012345678901234567890 1 PNPS AST - *FA- BOUNDING SRC - 24 HR DZCAY - RB VENT RELEASES - CR - 1000 CFM 2 10002 4 6 a 1 0 NNYNNY N NNN YYYYYY 3 10003 O 1.0 24.0 0.0 0.0 4 10004 3 0 0 S 1 :1.0003+00 .000X+00 .000+00 KR X8 6 2 2.8503-03 2.150E-03 .000e+00 BR I 7 3 .0000+00 .000oz00 .0003+00 ZZ 8 10006 -. 1.OOOZ+OO .000o+00 9 BR82 2.042B+02 DR82M 7.892E+01 BR83 2.567B+03 BR84 4.7333+03 10 BR84M 1.328B+02 BR85 5.8158+03 8R86 4.356B+03 BR87 9.921Z+03 11 BROS 1.130Z+04 12 1128 5.702B+02 1129 1.793R-03 1130 1.3833+03 I130M 5.402X102 13 1131 2.7173+04 1132 2.4113+04 1133 3.4171+04 1134 3.8151+04 14 1134M *.074B+03 1135 3.1821+04 1136 1.544E+04 1136M 9.4461+03 15 1183 ;2.567B+03 KR85 8.551.+02 3S85K 5.880+03 1R87 1.175S+04 16 XR88 1.6621+04 XR89 22.096Z+04 SR90 2.081Z+04 17 XE131M 1.905E+02 XE133 3.4173+04 X3133K 1.0523+03 X8135 1.744Z+04 18 XZ135M 5.8253+03 XZ137 3.0073+04 X1138 3.037E+04 XE139 2.4471+04 19 10007 2 7.03+05 96.0 0.0 0.0 0.0 0.0 'Refueling Level, 20 10009 2 34280.0 1000.0 0.0 0.0 0.0 0.0 'Control Room' 21 10010 4I 22 0.0 -40.5 1.0 720.0 23 10018 5 24 0.0 1.7603-03 2.0 1.2501-03 8.0 4.2603-04 24.0 3.6701-04 96.0 3.1501-04 25 10021 L 26 0.0 3.5Z-04 27 10024 3 28 0.0 1.0 24.0 0.6 96.0 0.4 29 99999 30 PNPS AST - FHA - BOUNDING SRC - 24 BR DECAY - RB VENT REL8ASZS - CR - 9000 CFM 31 10002 4 6 8 1 0 NNYNM N MNN YYYYTY 32 10003 0 1.0 24.0 0.0 0.0 33 10004 3 0 0 34 1 1.0000Z+0 .OOO+.00 .OOO+00 3R XB 35 2 2.850B-03 2.150Z-03 .0001+00 BR I 36 3 0.000+00 .00O0Z00 .0001.00 zz 37 10006 -1.000B+00 .000X+00 38 bR82 2.0423+02 BR82M 7.992Z+01 BR83 2.5671+03 BR84 4.7333.03 39 BR84M 1.3288+02 BROS 5.815B+03 BR86 4.356E+03 BR87 9. 9213+03 40 BR88 1.130X.04 41 1128 5.702B+02 1129 1.7938-03 1130 1.3833+03 I130M 5. 4023+02 42 1131 2.7178+04 1132 2.411E+04 1133 3.417E+04 r134 3.8153+04 43 1134M 4.074Z+03 X135 3.182Z+04 1136 1.5448+04 X136M 9. 446E+03

A PNPS- Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 42 AR EVA 44 1R835 2.5675+03 XR85 8.5513+02 5RO5H 5.8805.03 5R87 1.1755+04 45 FR88 1.662Z+04 XR89 2.096X+04 XR90 2.0813+04 46 X3131M 1.9053+02 Xe133 3.4175+04 X51335 1.0525E03 X3135 1*7443+04 47 X3135M 6.8255+03 X3137 3.0075+04 XZ138 3.0373+04 X3139 2.447E+04 48 10007 2 7.0X+05 96.0 0.0 0.0 0.0 0.0 'Refueling Level' ELXSA-2 CLzCBNSISa & BSVBRZ ACCIDENT RADZOLOGICAL EVALUATIONS - ESTZCH MM. - Rol. Version 2.2 Mnay 23,20021 28-Oot-04 PAGE 2 INPUT DATA LI8S1N Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345678901234567890123456789012345678901234567890123456789012345678901234567090123456789012345678901234567890 49 10009 2 34280.0 9000.0 0.0 0.0 0.0 0.0 'Control Rooc' 50 10010 4 51 0.0 0.5 1.0 720.0 52 10018 5 53 0.0 1.7603-03 2.0 1.2505-03 8.0 4.260z-04 24.0 3.6705-04 96.0 3.150B-04 54 10021 1 55 0.0 3.5B-04 56 10024 3 57 0.0 1.0 24.0 0.6 96.0 0.4 58 99999

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

. Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 43 BLISA-2 [LICENSING SEVERE ACCIDENT RADIOLOGICAL ZVALVATIONS - ZNS8CH ZNG. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGE 3 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345C7890123456789012345678901234567890123456789012345678901234S678901234567890123456789012345678901234S67890 1 ZLISA-2 DATA LIBRARY - BASED ON ORIGEN-2 AND FEDERAL GUIDANCE REPORTS 12 AND 12 V2L1 1 2 RELEASE DATE: 6/28/2004 V2L2 1 3 RZMARKS (START) V2L1 3 A Source inventories are in Ci for the power level specifled for each plant. V2L1 4 S Decay constants are in inverse hourn. V2Ll 5 6 The entry line following the decay chains includes the decay constants V2LI 6 7 for each of three members (parent (P), daugher (D) and granddaughter V2Ll 7 8 (0)], and the branching fractions (P-D), (D-G) and (P-U). V2LMI 9 Air i= rsion DMs are in [((Dv or Gy))/s)/(Bq/m3)3, for semi-infinite cloud V2Ll 9 10 Ground-shine DCa are in t((Sr or Gy))/s)/(Bq/n2)) (surface contamination). V2Ll 10 11 Inhalation DCFa are in (Sr/Bq)J. V2Ll 11 12 The inhalation DCF' are for the Lung Clearance Class which yields the V2Ll 12 13 highest Effective Dose Equivalent (Eff D.3.)j the class is identified. V2L1 13 14 Negative DCr entries imply 'data not available,. V2L1 14 15 ORGAN 'TID Thy' - Thyroid inhalation based.on TXD-14844 - Iodine. only. V2L1 1S 16 ORGAN 'RG1109WB' a Whole body gama done using the Reg. Guide 1.109 DCrs. V2L1 16 17 Skin DCrn are Included along with the organ DCs, but skin is not V2L1 17 18 considered as an organ. V2Ll 18 19 6/28/2004 V2L2 2 20 Added beta MeV/dis for BROS, XR89, KR90, RM90M, RB90, 1136, Xel37 & CS-139 V2L2 3 21 (Based on Kocher, DOZ/TIC-11026, Radioactive Decay Data Tables (1981) V2L2 4 22 RRAD FORMATS FOR THE RADIONUCLIDE DATA BASE V2Ll 19 23 Line 1 Nuclide name and nource inventories (4x,a6,l0x,4el2.3) V2Ll 20 24 (Note: Nuclide sequence No. is not used) V2Ll 21 25 Line 2 Header (ago) V2LI 22 26 Line 3 Decay chain (3 members) (9x,3(a6,6x)) V2Ll 23 27 Line 4 Decay constants & branching fractions (Ox,6el2.3) V2LM 24 28 Line 5 Reader (a8O) V2L1 25 29 Lines 6-9 18 ORIGEN-2 photons and 1 ICRP-38 beta (8x,6e22.3) V2Ll 26 30 Line 10 Header (a8O) V2Ll 27 31 Lines 11-16 Dose conversion factors (8x,6el2.3) V2Ll 28 32 END REMARKS V2L1 29 33 GENERAL DATA BASE V2Ll 30 34 10 [ORGAN NAMES - READ FORMAT (llx,6(a8,4x))I V2L1 31 35 Gonads Breast Lungs R.Narrow Bone Sur Thyroid V2L1 32 36 Remaindr eff D.E. TID Thy RG1109WB (Skin) V2Ll 33 37 4 (Pow r plants and power levels (MWt) - READ FORMAT (1lx,a20,lx,el2.3) V2LI 34 38 PWR (33 GWD/MT 3.2') 1.0003+00 VMLI 35 39 PWR (50 GWD/NT 4.2%) 1.OOOE+00 VMl1 36 40 BWR (27.5 GWD/MT 3S) 1.O00E00 V2Ll 37 41 BWR (40 OWD/MT 3.4%) 1.000+O00 V2L1 38 42 18 [ORIGEN-2 upper limit energy in each ganma group (NeV) (Sx,6e12.3)j V2L1 39 43 2.000Z-02 3.000Z-02 4.500E-02 7.0003-02 l.00OZ-01 1.500Z-01 V2L1 40

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by. John N.Hamawi Document ID32.5052589-01 Page 44 AREVA 44 3.0003-01 4.500-018 7.0003-01 1.OOOZ+OO 1.5003.00 2.0003+00 V2L1 41 45 2.500E+00 3.000+00 4.0003+00 6.0005+00 8.000E+00 1.1003+01 V2L1 42 46 3 Factors to convert data library DCFe to proper units, an shown V2LI 43

7 1.0 Convert air inmmrsion DCX to (((Sv or Gy)/u)/(Bq/m3)] V2LI 44 48 1.0 Convert ground nhino DCx to 1((By or or)/&)/(Bq/m2)3 V2L1 As ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL XVALUATIONS - ENTECH MNM. - Rol. Veruion 2.2 Kay 23,200231 28-Oct-04 PAGE 4 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345678901234567890123456789012345678901234567890123436789012345678901234567890123456789012345678901234567890 49 1.0 Convert inhalation DC? to Isy/Bq] V2L1 46 50 18 Air ga-a DCF for semi-infinite monoener. cloud arc [((y/s)/(Bq/m3)] V2L1 '7 51 6.676Z-16 1.669E-15 2.503Z-15 3.839B-15 5.674Z-15 8.345Z-15 V2L1 48 52 1.5023-14 2.5033-14 3.839Z-14 5.6741-14 8.345E-14 1.1683-13 V2L1 49 53 1.5023-13 1.836Z-13 2.337Z-13 3.3383-13 4.6733-13 6.3423-13 V2L1 50 54 18 Air ga=m DCx for monoenerg. ground-surface source C(ay/s)/ (q/12)] V2L1 51 55 1.8293-16 1.4933-16 9.8353-17 8.181Z-17 9.767Z-17 1.436E-16 V2L1 52 56 2.760Z-16 4.7853-16 7.3185-16 1.050E-15 1.4573-15 1.9103-15 V2L1 53 57 2.3253-15 2.710Z-15 3.2433-15 4.194E-15 5.386E-15 6.759E-15 V2L1 54 58 18 Skin gaem DCZ for semi-infinite monoener. cloud *rc t(Sv/n)/(Bq/m3)3 V2LI. 55 59 1.138E-16 7.6903-16 1.467z-15 2.717E-15 4.416Z-15 6.737E-15 V2L1 56 60 1.239B-14 2.0738-14 3.193E-14 4.7543-14 7.1083-14 1.0123-13 MIL 57 61 1.3173-13 1.6248-13 2.0893-13 3.030Z-13 4.305Z-13 5.922E-13 V2L1 58 62 RADIONUCLIDE DATA BASE V2L1 59 63 I R 3 (treCi) 1.4713+01 2.1863+01 1.744E+01 2.5363+01 V2L1 60 64 Decay chain, decay constants and branching fraction. V2L1 61 65 3 V2L1 62 66 6.403203-06 .00000+00 .OOOOO+00 .0003+00 .0005+00 .OOOE00 V2L1 63 67 ORIGHN-2 18-group phot/die, and ICRP-38 betas (MoV/die) V2L1 64 68 .0005+00 .00OZ+00 .000+00 .000t00 .0003+OO .0005+00 V2L1 65 69 .000+00 .OOO+00 .OOOE400 .0003+00 .0003+00 .OOO+00 V2L1 66 70 .0003+00 .0003+00 .0005+00 .OOO00 .0003+00 .OOO+00 V2L1 67 71 5.600Z-03 V2L1 68 72 ICRP-38 Organ DCFs - Air l4-er, Grnd shine, Inbal/Claee V V2L1 69 73 .0005+00 .000+.00 2.750E-18 .0005+00 .000E+00 .0003.00 V2L1 70 74 .0003+00 3.310Z-19 .0003+00 .OOO+00 .OOOE300 V2L1 71 75 .0003+00 .000z+00 .0005+00 .0003+00 .0005+00 .0003+00 V2L1 72 76 .0005+00 .0003+00 .000Z+00 .00oz+00 .0003+00 V2L1 73 77 1.730Z-11 1.730Z-11 1.7303-11 1.7303-11 1.730E-11 IL.730E-11 V2L1 74 78 1.730Z-11 1.7303-11 .000.+00 .0003+00 V2L1 75 79 2 C 14 (Src Ci) 3.125Z-06 4.723Z-06 3.772Z-06 5.467E-06 V2L1 76 80 Decay chain, decay constants and branching fractions V2L1 77 81 C 14 V2L1 78 82 1.38016Z-08 .000003+00 .000003+00 .0003+00 .0003+00 .ooo0+oo V2L1 79 83 ORIGEN-2 18-group pbot/dis, and ICRP-38 beta. (MeV/dis) V2L1 80 84 .0003+00 .0008+00 .0003+00 .0003+00 .00O0+00 .0003+00 V2L1 81 85 .0oooeoo .0003+00 .000o.00 .0003+00 .OOO0oo .000+.00 V2L1 82 86 .000*+00 .0003+00 .0003+00 .000+.00 .0003.00 .0003+00 V2L1 83 87 4.940E-02 V2L1 84

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 45 ARE VA 88 ICRP-38 Organ DCFr - Air immer, Grad shine, Tnhal/Clagg c V2L1 85 89 2.590Z-19 3.5201-19 1.5301-19 1.210Z-19 7.0601-19 2.190B-19 V2L1 56 90 1.5401-19 2.2401-19 .0001+00 .000R+00 2.4301-16 V2L1 87 91 2.2201-20 2.520Z-20 8.650Z-21 7.2501-21 4.6301-20 1.250Z-20 V2L1 88 92 1.030B-20 1.6101-20 .0001+00 .0001+00 7.4601-20 V2L1 89 C.... etc., for a total of 414 radionuclides .... ,

A A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R EVA Prepared by: John N.Hamawi Page 46 RLISA-2 [LICENSING SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ZNTICE 1NG. - Rol. Vorajon 2.2 Nay 23,20021 28-Oct-04 PACE 5 CASIO 1 PUPS AST - FRA - BOUNDING SRC - 24 UR DECAY - RE VENT RELEASIS - CR - 1000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

LISTING OF INPUT DATA PAThWAY OPTION 4 A (COMP. A -- > COMP. C)

COMPARTMENT A: Refuellng Level TOTAL FREE AIR VOLUME (cu ft)

7.0001+05 FILTERED RECIRCULATION RATE (cfm) * .0001+00 LEAK RATE TO ATMoSPHERE (frac/day)

9.600X.01 COMPARTMENT C: Control Roon TOTAL FREE AIR VOLUME (cu ft) - 3.4281+04 INTAKE AND MXHAUST RATES (cfm) a 1.0001+03 rILTERED RECIRCULATION RATS (cWm) = .OOO+00 FILTER REMOVAL ErFIcIENCIES AND TIME-DEPENDENT MULTIPLIER FOR RECIRCULATION RATES, LEAR RATES, COMP. A FLOW RETOEEN SPRAYED AND UNSPRAYED AREAS, AND FILTER BYPASS FRACTIONS ARE GIVEN BELOW.

NO. OF DISCRETE TIME VALUES IN INPUT a 8 INTERMEDIATE RESULTS WILL BE PRINTED AT THE FOLLOWING TIMES (bra):

.0000+00 5.0000Z-01 PROBLEM END TIME (hours)

7.20001+02 RELEASE RATES AND DOSE RATES ARE PRIOR TO TIMZ-STEP CHANGES, IF ANY.

ONLY EXACT SOLUTION OF THE DIFFERENTIAL EQUATIONS WAS EMPLOYED IN THE ANALYSIS.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32.5052589-01 Page 47 AR EVA ELISA-.2 LICmNSINm & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTZC8 ENO. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 6 CASR 1 PNPS AST - TFA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

RECIRCULATION, EXHAUST AND INTAMM FILTER RZMOVAL RFrICIENCIES (fractions)

COMPARTMENT A RECIRC. COMPARTMENT B RECIRC. COMPARTMENT C RECIRC. Z*XAUST TO ATMOSPHBRZE NTAK3 TO COMPART. C N UCL.-FF 1 O 2-----3O-O 2F1--------- -- --- -- -- -- - -- -- -- -- - R F-----M FR

----- -- I--- FO--- 2--------ORM----------

GROVP FORM I FORM 2 FORM 3 FORM 1 FORM 2 FORM 3 FORM I FORM 2 FORK 3 FORK l. FoRM 2 FORM 3 FORM I FORM 2 FORM 3 1 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 2 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 3 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 UEMR-SPECIFIND CLASSIFICATION OF RADIONUCLIDES AND INSTANTANEOUS FRACTIONAL RELEASES FROM STI SOURCE (AT T-0)

GROUP E L E N N N T S FORM 1 FORM 2 FORM 3 1 KR XZ 1. 000+.00 .000+00 .000x+00 2 BR r 2.8501-03 2.150B-03 .OOOE+00 3 zz .0001+00 .000x+00 .000z+00 ELEMENT 'ZZ" STANDS FOR THE REMAINING DATA-LIBRARY ELEMENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

AA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 48 ELISA-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTICH MNM. - Rel. Verblon 2.2 May 23.2002] 28-Oct-04 PAGE 7 CASH# 1 PNPS AST - YEA - BOUNDING SRC - 24 ER DECAY - RD VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RELEAS9 FROM SOURCE)

TIME INTERVAL CONCZNTR. CAMMA DEPOSITION BREATHING eM. PILT. COMPART. C COMPART. C X/Q X/Q D/Q RATE BYPASS INT.FrILTER OCCUPANCY (hourn) (sec/=3) (sec/m3) (1/n2) (m3/sec) FRACTION BYPASS FR. FACTOR

.00001+00 - 5.0000Z-01 1.760B-03 1.760E-03 .00O1.00 3. 500B-04 .0oooe00 .OOOE094 1.0001+00 5.0000-01 - 1.0000o+00 1.7601-03 1.760R-03 . 000+00 3.300E-04 ., 0ooo+oo .OOO+00 1.0001+00 1.0000+00 - 2.0000Z+00 1.760B-03 1.760B-03 . 000Z00 3.5001-04 .000E+00 . ooo+00 1. 000.00 2.0000+E00 - 8.00001+00 1.290-03 1.250E-03 .000z+oo 3.3001-04 . 0001+00 . 00O0+00 1.0001.00 8.00001+00 - 2.4000B+01 4.2601-04 4.2601-04 .000E+00 3.500s-04 .000B+00 .0001+00 1. o0o0000 2.40001+O1 - 9.6000R+01 3.670B-04 3.6708-04 .0001.00 3.500B-04 .0001+00 .0001+00 6.000R-01 9.60001+01 - 7.2000E+02 3.150l-04 3.1501-04 .00OZ+00 3.5001-04 .000H+00 .0003+00 4 000Z-01 TIME INTERVAL COMPAMT A MULTIPLIERS COMPART B MULTIPLIERS COMPART C MULTIPLIERS FLOW MULT.

(IF APPLICABLE) (IF APPLICABLE) (IT APPLICABLE) SPRAYED AREA (hours) LEAK RATE RIc.rxLTIR LEAK RATE RzC.FriLR INTAKEB/BI RBC.F1LTHR TO UNSPRAYED

.00001.00 - 5.00001-01 1.O000+00 1.000Z+00 1.0001+00 1.000+00 1.o000+00 1. 0001+00 1.O000+00 5.0000B 1.0000Z+OO 1.000Z+00 1. 000B+00 1. 0001.00 1.0001.00 1.0001+00 1.0001+00 1.00O1.00 1.0000B.00 - 2.0000O+00 1.0001+00 1. 000+00 1.000+00Z+ 1.0001+00 1.0001+00 1.000C+00 1. 0001+00 2.00001+00 - 8.0000Z+00 1.0001+00 1.0001+00 1.000B+00 1.0001+00 1.0003+00 1.0001+00 1.000Z+00 8.00001+00 - 2.4000X+01 1.0001+00 1.0001.00 1.0001+00 1.0001+00 1.0001+00 1.0001+00 1.000Z+00

2. 4000R+01 - 9.6000B+01 1.000B+00 1. 000+00 1.0001+00 1.0001+00 1.000R+00 1.000e+00 1.000+E00 9 6000z+01 - 7.2000E+02 1.000,+00 1. 000E+00 1.0001+00 1.0001+00 1. 000e+00 1. 000Z+00 1. 0001+00

AA A R EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 49 ELISA-2 (LICENSING & 8EVERE ACCIDENT RADIOLOGICAL 3VALUATIONs - ENTECH MNM. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGE 8 CASE# 1 PNPS AST - FRA - B0UNMING SRC - 24 HR DECAY - RB VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

U88R-SPECIFIED SOURCE INVENTORY NUCLIDE GROUP (CL) NUCLIDE GROUP (Ci) NUCLIDE GROUP (CL)

BR 82M 2 7.89203+01 IR 87 1 1.17503+04 1134 2 3.8150C+04 BR 82 2 2.0420E+02 KR 88 1 1.66203+04 1135 2 3.18203+04 BR 83 2 2.56703+03 KR 89 1 2.0960E+04 1136K 2 9.4460E+03 BR 84K 2 1.3280E+02 KR 90 1 2.0810E+04 1136 2 1.5440E+04 BR 84 2 4.7330E+03 1128 2 5.70203+02 XZ131M 1 1.90505+02 BR 85 2 5.B150.+03 1129 2 1.7930R-03 XB133N 1 1. 05203+03 BR 86 2 4.35603+03 1130H 2 5.40203+02 XB133 1 3.41705+04 BR 87 2 9. 92103+03 1130 2 1.38303+03 XB135M 1 6.8250Rt03 BR 88 2 1.13003+04 1131 2 2.71703+04 X3135 1 1.74403+04 KR 83N 1 2.56708303 1132 2 2.41103+04 X3137 1 3.00703B04 KR 85M 1 5.88003+03 S133 2 3.4170E+04 X3138 1 3.03703+04 KR 85 1 8.5510E+02 11343 2 4.07403i03 X3139 1 2.44703+04 ELISA-2 [LICENSING & S9VERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTxCr ENO. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAGE 9 CASE# 1 PNPS AST - FHA - BOUNDING SRC - 24 RR DECAY - RB VENT RELEASES - CR - 1000 CYN (INSTANTANEOUS RELEASE FROM SOURCE)

SOURCE INVENTORY FOLLOWING 2.4003o01 HOURS Or RADIOACTIVE GROWTH AND DECAY PRIOR TO RZLEASE NUCLIDE GROUP (CL) NUCLIDE GROUP (Ci) NUCLIDE GROUP (Ci)

BR 82 2 1.27613+02 SR 89 3 9.01503-01 XE133M 1 9.4669E.02 BR 83 2 2.4352E+00 1128 2 2.5419Z-15 XE133 1 3.2869E+04 BR 84 2 1.10573-10 1129 2 1.79303-03 XE135M 1 4.1160E+02 KR 83M 1 9.44453.00 1130N 2 3.69638-46 X3135 1 9.60503+03 KR 85M 1 1.45053+02 1130 2 3.61473+02 XZ138 1 7.7776e-27 KR 85 1 8.55013+02 1131 2 2.49263+04 C9135 3 6.60143-06 KR 87 1 2.47293-02 2132 2 1.74193+01 CS137 3 7.2987Z-03 KR 88 1 4.7443Z+01 1133 2 1.5357+.04 C8138 3 8.23373-10 RB 87 3 3.6297E-11 1134 2 2.1896Z-04 C8139 3 1.41358-43 RB 88 3 5.2925E*01 1135 2 2.56973.03 BA137M 3 6.904S8-03 RD 89 3 1.6731B-25 X3131M 1 1.96063+02 DA139 3 1.2700R-03

I A,ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Altemative Source Term Methodology (2038 MWI)

Document ID32.5052589-01 A R EVA Prepared by. John N.Hamawi Page 50 ZLISA-2 fLICENSnr3 & SEVERE ACCIDENT RADIOLOGICaL EVALUATIONS - ENTSCR ENO. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAGE 10 CASEt 1 PNPS AST - FA - BOUNDING SRC - 24 UR DECAY - RB VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RMLZASB PROM4 SOURCE)

FINITZ-CLOUD COLRECTION PACTORS FOR GAMMA RADIATION EXPOSURRS COMPARTMENT A COMPARTMSNT B COMPARTMENT C HEMISPRE. CLOUD SPHERICAL CLOUD HNISPHE. CLOUD NUCLSDE RADIUSe 21.1S M RADIUS- .00 N RADIuSw. 7.74 M BR 82 7.095s-02 .0003+00 2.605Z-02 BR 83 7.408Z-02 .000E.+O 2.7453-02 BR 84 5.9903-02 .0003+00 2.206B-02 KR 83N 9.9523-01 .0008+00 9.7833-01 KR 85s 7.8343-02 .OOOE+00 3.1031-02 KR 85 7.486E-02 .000+00 2.7443-02 KR 87 6.1781-02 .0003+00 2.2693-02 XR 88 6.010B-02 .000B00 2.2473-02 Rs 88 6.206B-02 .OOO+00 2.2863-02

.1128 8.2072-02 .OOO+00 3.0583-02 1129 4.8793-01 .OOO+100 2.1408-01 11303 1.0393-01 .0003.00 4.14SE-02 1130 7.338-02 .000+00 2.691B-02 1131 7.672e-02 .0003+00 2.8093-02 1132 7.2031-02 .000o+00 2.6A4Z-02 1133 7.371n-02 .0003+00 2.703e-02 1134 7.0243-02 .000+00 2.5793-02 1135 6.5491-02 .000.+00 2.4091-02 XB1313 4.5189-01 .0003+00 2.0213-01 XR133H 2.6281-01 .OOO+00 1.1371-01 X3133 1.3533-01 .0003+00 4.8781-02 X31353 7.9183-02 .0001+00 2.9421-02 XE135 7.4541-02 .000+00 2.6513-02 X3138 6.3053-02 .000+00 2.329B-02 C5138 6.4593-02 .0001+00 2.3763-02 MnRPHY/CAMPE 8.060e-02 .0003+00 2.908e-02 (0.733 MEV - INPORMATION ONLY)

PURE BETA EMITTERS AND RADIONUCLIDES wITm uNDFIrNED GAMMA SPECTRA ARE EXCLUDED FROM THE ABOVE LIST.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWQ)

Prepared by'. John N.Hamawi Document ID32-5052589-01 Page 51 AR EVA ELISA-2 [LICENSNGO & SEVERE ACCIDENT RADIOLOGICAL WVALUATIONS - ENTCEH ZNO. - R.l. Version 2.2 May 23,2002J 28-oct-04 PACE 11 CASE# 1 PRPS AST - FEA - BOUNDING SRC - 24 RR DECAY - RB VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RILKASI FROM SOURCE)

T - OOOOE+00 hra DISTRIBtJTION OF RADIOACTIVITY NUCLIDS COMPARTM. CHEM-SPRAY REC.FILTER COMPARTH. REC.FILTSR 8XH FILTER COMPARSM. INS. FILTER REC.FILTER A IN COMP. A IN COMP. A B in COMP. n TO ATMOSP. C TO COMP. C IN COMP. C (Ci/m3) (Ci) (Ci) (Ci/=3) (CL) (C1) (Ci/m3) (Ci) (Ci)

DR 82 3 2191-05 .0001+00 .0002+00 .0001+00 .0001+00 .0001.00 .0001+00 .000Z+00 .0001+00 DR 83 6.143E-07 . 000e.00 .0001+00 .OOO+00 .0001+00 .0001+00 .0008+00 .0001+00 .0001+00 BR 84 2.789B-17 . 0001o00 .0001+00 .OOO+00 .0001+00 .0001.00 .000X+00 .OOO+00 .0001+00 KR 83H 4.765E-04 000E+00 . 0001+00 .OOO+00 .0001+00 .0001+00 .000Z+00 .OOO+00 . 0001+00 KR 85M 7.318B-03 .0001+00 .0001+00 .OOO+00 .000N+00 .0001.00 .OOO+00 .0008+00 .OOO+00 KR 85 4.3141-02 . 0001+00 .0001+00 .0001+00 .0001+00 .0001+00 .OOO+OO .0001+00 .000+.00 KR 87 1.2 48-06 .000+00 . 0001+00 .0001+00 .0001+00 *0001.00 .0001+00 .OOO+00 .000+00 KR 88 2.3941-03 . 000+00 .000+00 .0001400 .0001+00 .OOO+00 .0001+00 .0001+00 .0001+00 1128 6.412E-22 0001+00 .0001+00 .0001+00 .0001+00 .0001+00 .000oo00 .0008+00 .0008+00 1129 4.523B-10 . 0001+00 .0001+00 .OOO+OO .0001+00 .OOO+.00 .000N+00 .0001+00 .0001+00 1130H 9.324Z-53 .000+00 .0001+00 .OOO+00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 1130 9. 118-05 . OOO100 .0001+00 .0001+00 .0001+00 .0001+00 .000Z+00 .0001+00 .0001+00 1131 6.288B-03 .000Z+00 .000+.00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 1132 4.394B-06 .0001+00 .ooo0+00 .0001+00 .0001+00 .0002+00 .OOO+00 .0001+00 .000+00 1133 3.874E-03 .000+00 000Z+00 . 0001+00 .0001+00 .0001.00 .000X+00 .00O0+00 .000+00 1134 5.523K-il .00OX+00 .0001+00 .000+00 .0001.00 .0001+00 .0001+00 .0001+00 .0001+00 1135 6.482E-04 .0001+00 .0001+00 .0001+00 .0001+00 .0001.00 .000+00 .0001+00 .000+00 XE131M 9.891E-03 .0001+00 .0001+00 . OOO+00 .0001+00 .0001+00 .0001+00 .0001+00 .OOO00 XZ133M 4.776Z-02 .0001+00 .000+00 .oooe+00 .0001+00 .0001+00 .0001+00 .000+00 .0001+00 XR133 1.6581+00 .0001+00 0001+00 .0001+00 .0001+00 .000Z+00 .000+00 .0001400 .0001+00 X1135H 2 077B-02 .0001+00 .0001+00 .000oo00 .0001+00 .OOO+00 .0001+00 .000+00 .000Z+00 XZ9135 4.8416z-01 .OOOE+00 .0001+00 .000o+00 .000E+00 .0001+00 .0001+00 .0001+00 .000+00 XE138 3.924B-31 .0001+00 .000+00 .OOO+00 .0001.00 .0008+00 .0001+00 .000+.00 .0001+00 TOTALS GROUP 1 2.2753+00 .OOOZ+00 .000+00 .0001+00 .000+00 .0001+00 .0001+00 .000E+00 .000+00 GROUP 2 1. 094-02 .0001+00 .0001+00 .0001+00 .000+00 .0008+00 .0001+00 .0001+00 .0001+00 GROUP 3 .0001+00 .OOO+00 .0001+00 .OOO+OO .000+00 .0001+00 .0001+00 . 000o+00 .000+00 GRND.TOT 2.2851+00 .0001+00 .0001+00 .OOO+00 .000.+00 .0001+00. .0001+00 .000.+00 .0001+00 THE COMPARTMENT VOLUMES (A, B AND C) IN THIS TABLE ARE t 1.9029+04 .000E+00 9.7079+02 (m3)

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 ARE VA Prepared by: John N.Hamawi Page 52 ELI8A-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECIK MM. - Rol. Version 2.2 May 23,20021 28-oct-04 PAGE 12 CASZ0 1 PNPS AST - F8A - BOUNDING SRC - 24 BR DECAY - RB.VENT RELEASES - CR - 1000 C'M (INSTANTANEOUS RELEASE FROM SOURCE)

T - .00008+00 hre RELEASE RATES TO ATMOSPHERE, INTERVAL RELEASES FROM .OOOOE+00 TO .00003+00 hra, CUMULATIVE RELEASES FROM 0.0 TO .00001C+00 hro, AND RADIOACTIVE-CLOUD CONCENTRATIONS WITHOUT DECAY IN TRANSIT WITH .0003+00 hra IN-TRANSIT DECAY REZL. RATE INTRV REL CVNL. REL CLOUD CONC REL. RATE INTRV REL CUML. REL CLOUD CONC NUCLIDE (Cl/hr) (CL) (Cl) (Ci/m3) (Cl/br) (Ci) (Cl) (Ci/m3)

BR 82 2.552E+00 .0003+00 .000v+00 1.2481-06 2.5528+00 .000+00 .0003+00 1.2489-06 BR 83 4*870Z-02 .0001+00 .000Z+00 2.3811-08 4.8701-02 .000R+00 .OOOE+00 2.381Z-08 BR 84 2.211Z-12 .0003400 .0008+00 1.081Z-18 2.2111-1.2 .000+00 .OOOB+00 1.081B-18 KR 83M 3.7783+01 .0003400 .000+00 1.8471-05 3.778Z+01 .000o+00 .0003+00 1.8471-05 KR 85M S.8023+02 .0003+00 .0008+00 2.837Z-04 5. 8023+02 .0008+00 .OOO+00 2.837Z-04 KR 85 3.420E+03 *0001.00 .0003+00 1.672Z-03 3.4203.03 .000+00 .0003,00 1.672Z-03 RR 87 9.8923-02 .000z.00 .0003400 4.836B-08 9.892Z-02 .ooo0+00 .0001+00 4.836B-08 KR 88 1.898B+02 .0001+00 .0003+00 9.278Z-05 1.8981+02 .0008+00 .0003+00 9.2781-05 1128 5.084E-17

0003.00 .0003.00 2.4853-23 5.084E-17 :.000z+0o .0003.00 2. 4858-23 1129 3.5868-05 .000E+00 .0001.00 1.753B-11 3.586Z-05 .0001+00 .0001+00 1.753Z-11 1130M 7.3933-48 .0001+00 .0001.00 3.6143-54 7.393Z-48 .0003.00 .0001.00 3.614E-54 1130 7.229Z00 .000H400 .000E+00 3.5341-06 7.229E+00 .0003+00 .0001+00 3.534Z-06 1131 4.9851.02 .0001.00 .0003+00 2.4371-04 4.9851+02 .0003+00 .0OOO+00 2. 4371-04 1132 3.484R-01 . OOO+00 .0001+00 1.703Z-07 3.4843-01 . 0001+00 .0001+00 1.7033-07 1133 3.0711+02 .0001+00 .0003+00 1.502B-04 3.0711+02 .000+00 .0003+00 1.502B-04 1134 4.379B-06 .0003+00 .0003+00 2.141Z-12 4.3793-06 .000+00 .0003+00 2.1413-12 1135 5.139B+01 .0OOO+00 .0003+00 2.513B-05 5.139Z+01 .0003+00 .0OOO+00 2.513Z-05 XZ131M 7.843E+02 .OOO+00 .0003+00 3.834E-04 7.843Z+02 .0001+00 .0003+00 3.8341-04

. 0003.00 XZ133M 3.787Z+03 .OOO+00 .0001.00 1.851Z-03 3.787Z+03 .0OOO+00 .0001+00 1.8513-03 X8133 1.315Z105 .0003+00 .000Z+00 6.4281-02 1.3153+05 .0003.00 .0003+00 6.4283-02 X113SM 1.6461+03 .0003.00 8.049B-04 1.6461+03 .000+00 .000z+00 8.0493-04

.0001.00 XZ135 3.842N+04 .000Z+00 1.8783-02 3.8423+04 .0003+00 .0001+00 1.8788-02 XZ138 3.111B-26 .0003.00 .0008+00 1.521Z-32 3.111E-26 .0001+00 .0003.00 1.521B-32 TOTALS GROUP 1 1.8031+05 .0003+00 .0003+00 8.817Z-02 1.8033+05 .0008+00 .0001.00 8.8171-02 GROUP 2 8.672Z+02 .0003.00 .0003+00 4.2401-04 8.6723+02 .000Z+0O .0003400 4.2401-04 GROUP 3 .OOO+00 .000E+00 .0003+00 .0OOO+00 .0003.00 .0001+00 .0003+00 .000o+00 GRND .TOT 1.8123+05 .OOOE+00 .0008+00 8.859Z-02 8 1.812Z+05 .000+00 .0003+00 8.859Z-02 NOTEi THE ATMOSPHERIC CONCENTRATION OF RADIOACTIVITY 1S BASED ON A DISPERSION FACTOR (X/Q) OF 1.7603-03 (sae/m3)

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawt Document ID32.5052589-01 Page 53 AR EVA ELISA-2 (LICENSING A SEVERE ACCIDZNT RADIOLOGICAL EVALUATIONS - ENTECE BNO. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGE 13 CASXO I PNPS AST - RA - BOUNDING SRC - 24 iR DECAY - RR VENT RELEASES - CR - 1000 CYM (INSTANTANEOUS RELEASE FRON SOURCE)

T = 5.0000B-01 bra DISTRIBUTION OF RADIOACTIVITY NUCLIDE COMPARTH. CEZY-SPRAY RRC.FILTER COMPARTS. REC.FILTER MM.FILTER COMPART5. INS. FILTER REC.FILTER A IN COMP. A IN COMP. A B IN COMP. B TO ATMOSP. C TO COMP. C IN COMP. C (Ci/m3) MCU) (CL) (CL/mn3) (CL) (CL) (Cd/m3) (Ci) (CI)

BR 82 4.3124-06 .000v+00 .0001Z00 .0001.00 .0001+00 .000-0 2.7061-07 .0001+00 .0001+00 BR 83 7.191Z-08 .000z+00 .0001+00 .0001 +00 .000.+00 .0001+00 4.5109-09 .000oo00 . OOO+00 BR 84 1.963Z-18 . OOO+OO .0001+00 .0001+00 .OOOB-00 .OOO+00 1.231Z-19 .0001+00 .000x+00 KR 83M 6.190Z-05 .OO0.OO .0001.00 .oooe+00 .0001.00 .0001+00 3.4851-06 .0001+00 .0001+00 XR 85M 9.166Z-04 .0001.00 . 0001+00 .0001+00 .0001+00 .0001+00 5.7491-05 .0001+00 .0001+00 KR 85 5.838Z-03 .000+00 .0001+00 .000+Z00 .0001+00 .0001+00 3.6618-04 .0001+00 .000+00 KR 87 1.286Z-07 .0001.00 .000+00 .000X+00 .00O0100 .0001.00 8.0638-09 .0001+00 .0001+00 KR 88 2.867Z-04 .*000100 .0001+00 .000Z+00 .0001+00 .OOOE+00 1.7988-05 .0001+00 .000x+00 RD 87 1.2441-22 .0001+00 .OOO+00 .OOO+00 .000X+00 .0001o00 7.804E-24 .0001+00 .OOO100 RD 98 2.077Z-04 .00OZ+00 .0001.00 .000oo00 .0001+00 .000w.00

.OOON+OO 1.3031-05 .0001+00 .0001+00 1128 3.775Z-23 .000B+00 .000+.00 .000o+00 .0003+00 .0001+00 2.3681-24 .0001+00 .0001+00 1129 6.121B-11 . 0001+00 .0001+00 .0003.00 .0001+00 3.839B-12 .0001+00 .0001+00

.0001,00:

X130H 1.2521-54 .000+.00 .0001+00 .0ooo+00 .0001+00 7. 852E-56 .0ooo+00 .0001+00

.0001.00 1130 1.200E-05 .0001+00 .0001.00 .000o+00 .0001+00 7.526Z-07 .000o+00 .0001+00 1131 8.4941-04

.0003+00

000+.00 .000+00 .OOO+00 .OOO+00 5.3271-05 .0001+00 .Ooo0+00

.0001.00 1132 5.115-07 .OOOE+00 .000+00 .OOO+00 .0001+00 .OOO+00 3.208B-08 .0001+00 .000+.00 1133 5.156Z-04 .0001+00 .0001+00 .0001+00 .OOO+00 3.234B-O5 .0001+00 .OOOE+00

.0001.00.

1134 5.0341-12 .0001.00 .0001+00 .000z+00 .0001.00 .OOOE+00 3.1571-13 .OOOE+00 .OOO+100 1135 8.3251-05 .0001.00 .OOO+00 .0001+00 .OOO+100 5.2211-06 .0001+00 .0001+00

.0001+00 XB131M 1.3441-03 .000E+00 .0oooe00 .0001+00 .0001.00 8.398Z-05 .0001+00 .0001+00

.0001.00 XB133N 6.484X-03 .0001+00 .OOO+00 .000X+00 .OOO+00 4.0381-04 .0001+00 .0001+00

.0001+00 XB133 2.2471-01 .OOO+OO .OOO+00 .OOO+00 .0001+00 1.4051-02 .0001+00 .OOO+00 XZ135M 8.198B-03 .0001+00 .0001+00 .OOO+OO .0001+00 .0001.00 1.349E-04 .OOOo00 .0001+00 XE135 6.501B-02 .000+00 .0001+00 .0008+00 .000+.00 .0001.00 3.994E-03 .0001+00 .0001+00 XZ138 1.2243-32 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 7.677B-34 .000K+00 .0001+00 CS13S 1.106E-12 .OOO+.00 .0001+00 .0001+00 .0001+00 .0001+00 6.938E-14 .0001+00 .000E+00 CS138 1.226Z-32 .OOOE+00 .OOO+00 .0001+00 .oooe+00 .000z+00 7.6899-34 .0001+00 .0001+00

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Termn Methodology (2038 MWt)

Document ID32-5052589-01 AR E VA Prepared by: John N.Hamawl Page 54 ELI8A-2 tLICENSI!NG SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH ZN3. - Rol. Version 2.2 May 23,20021 28-oct-04 PACE 14 CASE# 1 PNPS AST - FRA - BOUNDING SRC - 24 8R DECAY - RD VENT RELEASBS - CR - 1000 CPH (INSTANANEOUS RELEASE FROM SOURCE)

T = .OOOOE-01 hre DISTRIBUTION OF RADIOACT M TY NVCLlDE COMPARTH. CHZM-SPRAY REC.FILTER COXPARTH. REC.FILTER X1. FILTER COMPARTM. INT.YILTER REC.FILTER A IN COMP. A IN COMP. A a IN COMP. B TO ATMOSP. C To COMP. C IN COMP. C (CI/m3) (Cl) (CI) (CI/m3) (Cl) (CL) , (Cl/m3) (CW) (Ci)

TOTALS GROUP 1 3.128Z-01 .0003+00 .0003+00 .0003+00 .OOOE00 .000,+00 2.911Z-02 . 000+00 .000+00 GROUP 2 1.465E-03 .OOO+00 .000+00 .OOO+00 .000+00 ,000+00 9.189B-05 . 0003+00 .000o+00 GROUP 3 2.077Z-04 .0003+00 *000E.0O .OOOZ+0 .OOOZ+00 .0003+00 1.303Z-05 .0003+00 . ooo0+00 oRND.TOT 3.1453-01 .OOO00 .oooe0oo .oooz0oo .OOOE+00 .OOO+00 1.9223-02 .000+00 .*000300 THE COMPARTMENT VOLUMES (A, B AND C) IN THIS TABLE AR.7 1.9823.04 .0003+00 9.707Z+02 (m3)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 Page 55 A R E VA Prepared by: John N.Hamawi ELXSA-2 ILXCENSXNG & SEVERE ACCIDENTr RADIOLOOICAL EVALUATIONS - ENTECK ENO. - Rel. Version 2.2 May 23.20021 28-OCt-04 P'AGE 15 CAXS 1 PNPS AST - FHA - 8OUNDINO SRC - 24 MR DECAY - RB VENT RZLEASZS - CR - 1000 CPH (INSTANTANEOUS RELEASE FROM SOURCE)

T - 5.0000E-01 hrs RELEASZ RATZ9 TO ATMOSPHERE, INTERVAL RELEASES FROM .00001+00 TO 5.00003-01 hr..

CUMULATIVE RELEASES FROM 0.0 TO 5.00008-01 hre, AND RADIOACTIVE-CLOUD CONCENTRATIONs WXTHOUT DECAY IN TRANSIT WITH .0003+00 hr. IN-TRAN8IT DECAY REL. RATE XNTRV REL CUML. REL CLOUD CONC REL. RATS XNTRV REL CUML. REL CLOUD CONC NUCLIDE (Cl/hr) (CL) (Cl) (CL/m3) (CL/hr) (CO) (CM) (Ci/m3)

BR 82 3.4201-01 5.499Z-01 5.499B-01 1.6725-07 3.4203-01 5.4993-01 5.4993-01 1.6723-07 BR 83 5.702Z-03 1. 0023-02 1.002E-02 2.787E-09 5.702Z-03 1.0023-02 1.0025-02 2.787Z-09 BR 84 1.5568-13 3.873Z-13 3.873Z-13 7.609Z-20 1.556Z-13 3.873E-13 3.8731-13 7.609E-20 KR 83M 4.9085+00 7.898E+00 7.898E+00 2.3993-06 4.9083+00 7. 899E.00 7.8985+00 2.399Z-06 KR 85M 7.2683+01 1.2223+02 1.222Z+02 3.553Z-05 7.2683+01 1.222Z302 1.2223+02 3.5533-05

]R 85 4.6289+02 7.3933+02 7.3935+02 2.263E-04 4.6285+02 7.3931+02 7.3933+02 2.2633-04 XR 87 1.019Z-02 1.952Z-02 1.952Z-02 4.9833-09 1.019E-02 1.9521-02 1.9525-02 4.9835-09 XR 88 2.273E401 3.936Z+01 3.9363.01 1.1118-05 2.2733+01 3.9361+01 3.9363+01 1.111-05 RB 87 9.865Z-18 5.751Z-18 5.7511-18 4.8233-24 9.865E-18 5.7513-18 5.7513-18 4.8233-24 RB 88 1.647EO01 1.1913+01 1.1913+01 8.0503-06 1.647Z+01 1.1913+01 1. 1913+01 8.0508-06 1128 2.993Z-18 8.446R-18 8.4461-18 1.4632-24 2.9933-18 8.4465-18 8.4463-18 1.4638-24 1129 4.853E-06 7.7523-06 7.7523-06 2.3733-12 4.8533-06 7.7523-06 7.7523-06 2.373Z-12 1130M 9.926E-50 8.4603-49 8.460E-49 4.8533-56 9.9268-50 8.460E-49 8.4601-49 4.8533-56 1130 9.5143-01 1.5483+00 1.5485+00 4.651E-07 9.5141-01 1.548Z400 1.5481+00 4.6511-07 1131 6.735E+01 1.077E+02 1.0773+02 3.2923-05 6.7353+01 1.0775+02 1.0778+02 3.2921-05 1132 4* 055Z-02 7.1561-02 7.156B-02 1.983B-08 4.0553-02 7.1S6Z-02 7.1563-02 1.9835-08 1133 4.088X.01 6.601X+01 6.6013+01 1.9993-05 4.0883+01 6.6013+01 6.6013+01 1.9995-05 1134 3.991B-07 8.308Z-07 8.308Z-07 1.9515-13 3.991E-07 8.308Z-07 8.308Z-07 1.951Z-13 1135 6.6001.00 1.0911.01 1. 0913+01 3.227Z-06 6.600z+00 I.0915+01 1.0915+01 3.227Z-06 XS131M 1.0663+02 1.6963+02 1.6961+02 5.211Z-05 1.0663+02 1.6962+02 1.6963+02 5.2115-05 S8133M 5.1413+02 8.1843402 8.1841402 2.513Z-04 5.1413+02 8. 1841+02 8.1843+02 2.5135-04 XZ133 1.7823.Q4 2.842E+04 2.8421+04 8.7103-03 1.7821+04 2.8425+04 2.8425+04 8.710Z-03 XE135M 6.5003+02 4.595E+02 4.5951+02 3.178Z-04 6.5005+02 4.595Z+02 4. 595Z+02 3.1783-04 XE135 5.1543+03 8.248E+03 8.2485+03 2.5205-03 5. 1541+03 8.2483+03 8.248Z+03 2.5203-03 XZ138 9.705Z-28 4.346Z-27 4.346B-27 4.7453-34 9 .7058-28 4.3468-27 4.3465-27 4.745E-34 CS135 8.770Z-08 4.9538-08 4.853Z-08 4.2985-14 8.7708-08 4.8535-08 4.8531-08 4.28S3-14 C8138 9.7201-28 8.771Z-28 8.771Z-29 4.7525-34 9.7205-28 8.7715-28 8.7718-28 4.7525-34

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-505258901 A REVA Prepared by: John N.Hamawi Page 56 ELISA-2 (LICENSING a SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH RNa. - Rol. Version 2.2 May 23,2002] 28-Oct-04 PAGZ 16 CASE# 1 P1PS AST - FHA - DOUNDINO 8RC - 24 ER DECAY - RD VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

S

5.0000Z-01 bra RELEASE RATES TO AT1.0SPIERE, INTERVAL RELEASES FROM .00001+00 TO 5.0000Z-O1 hra, CUMULATIVZ RELEASES FROM 0.0 TO 5.0000-01 brs, AND RADIOACTIVE-CLOUD CONCENTRATIONS WITHOUT DECAY IN TRANSIT WITH .0002+00 bra ZN-TRANSIT DECAY REL. RATE SNTRV REL CUHL. REL CLOUD CONC REL. RATE xNTEV REL CDML. REL CLOUD CONC NUCMIDE (Cl/hr) (Ci) (Ci) (CL/m3) (Cl/hr) (Cl) (Ci) (Ci/m3)

TOTALS GROUP 1 2.4801+04 3.9028+04 3.9021+04 1.2133-02 2.4801+04 3.9021+04 3.9021+04 1.2131-02 GROUP 2 1.1621.02 1.8681+02 1.8681+02 5.679B-05 1.162E+02 1.8683+02 1.8681+02 5.679Z-05 GROUP 3 1.6471+01 1.1911+01 1.1911+01 8.050R-06 1.647B+01 1.1911.01 1.191B+01 8.050-06 GRND.TOT 2.4941+04 3.922E+04 3.9223+04 1.2191-02 2.494Z+04 3.922Z+04 3.922Z+04 1.2191-02 NOTE: THE ATMOSPEBRIC CONCENTRATION OF RADIOACTIVITY IS BASED ON A DISPERSION FACTOR (X/Q) OF 1.760B-03 (sac/m3)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 57 ARE VA ZLISA-2 tLICENSINO & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH RNO. - Rel. Verslon 2.2 May 23,20021 28-Oct-04 PACE 17 CAsE# 1 NPS AST - FEA - BOUNDING SRC - 24 RR DECAY - RR VENT RELEASES - CR - 1000 crn (INSTANTANEOUS RELzASz FROM SOURC8)

S - 5.0000E-01 brs EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (CONTINUOUS OCCUPANCY)

COMPARTMENT C (INTERVAL DOSES ARM FROM .0000R+00 TO 5.0000R-01 hrD)

Beta Air Beta Air Gata Air Gaa Air Tot. Skin Tot. Skin Thyroid Thyroid 8ff D.E. Eff D.E.

DOSE RATE SNTVL DOs DOSE RATE INTVL DOS DOSE RATE XNTVL DOS DOSE RATS INTVL DOS DOSE RATE INTVL DOS NUCLIDZ (rad/hr) (rad) (rad/hr) (rad) (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

BR 82 6.6893-05 2.7931-05 1.655B-05 6.908s-06 3.487Z-05 1.456z-05 1.2203-05 5.095R-06 1.2201-05 5.095R-06 BR 83 2.577z-06 1.1392-06 8.2333-10 3.6303-10 1.087R-06 4.8051-07 6.267E-10 2.7703-10 6.300Z-10 2.7843-10 BR 84 2.6918-16 1.489R-16 4.316Z-18 2.3883-18 1.4223-16 7.8663-17 3.437z-18 1.9011-18 3.4041-18 1.883z-18 KR 83N 2.399Z-04 1.058s-O4 7.8113-06 3.4463-06 1.6231-06 7.1593-07 2.920z-08 1.28S1-08 6.8123-08 3.005z-08 KR 85M 2.610B-02 1.121Z-02 2.508Z-04 1.077B-04 1.071B-02 4.601B-03 1.742E-04 7.4823-05 1.7783-04 7.6353-05 KR 85 1.631Z-01 6.782Z-02 1.972Z-05 8.2023-06 6.379s-02 2.653B-02 1.579Z-05 6.5651-06 1.592Z-05 6.6213-06 KR 87 1.s999-05 8.8633-O6 1.2903-07 6.022e-08 9.923Z-06 4.632E-06 1.007Z-07 4.6991-08 1.0041-07 4.688R-08 KR 88 1.16SE-02 5.099Z-03 7.0233-04 3.074E-04 5.7841-03 2.531Z-03 5.5441-04 2.4263-04 5.490E-04 2.4033-04 RB 87 1.546R-21 3.9111-22 .OOO+00 .000+00 3.274z-22 8.283e-23 .0001Z00 .0008+00 .0003+00 . 0001Z00 RB 88 4.786Z-02 1.399Z-02 1.664E-04 4.8633-05 2.5613-02 7. 484-03 1.337B-04 3.906Z-05 1.333Z-04 3.8943-05 1128 3.149Z-21 1.8s93-21 5.4863-24 3.2973-24 1.554E-21 9.3371-22 3.9833-24 2.394B-24 4.0123-24 2.4121-24 1129 4.3561-10 1.8111-10 1.802X-11 7.4953-12 2.3521-11 9.7823-12 4.224B-12 1.7563-12 4.1581-12 1.7293-12 1130M .0001400 .00O1+00 3.439Z-55 *.4373-55 2.7923-55 3.6021-55 .000+00 .000Z+00 .OOOZ+00 .0003.00 1130 3.978s-o0 1.6733-04 3.8553-05 1.6223-05 1.9961-04 8.396z-05 2.8053-05 1.180Z-05 2.805z-05 1. 180Z-05 1131 1.8161-02 7.5583-03 5.0733-04 2.1111-04 6.6251-03 2.757z-03 3.6073-04 1.501B-04 3.6271-04 1.509E-04 1132 2.8261-05 1.252B-05 1.7213-06 7.624R-07 1.440Z-05 6.378s-06 1.265s-06 5.605S-07 1.2653-06 5.605E-07 1133 2.3613-02 9.8873-03 4.717R-04 1.9753-04 1.094B-02 4.5823-03 3.4113-04 1.4281-04 3.422E-04 1.433E-04 1134 3.4941-10 1.721E-10 1.9023-11 9.3683-12 1.8141-10 9.937E-11 1.410E-11 6.9461-12 1.4103-11 6.946B-12 1135 3.408E-03 1.4483-03 1.761z-04 7.486e-05 1.6203-03 6.88S3-04 1.3423-04 5.703Z-05 1.3373-04 5.6812-05 XB131M 2.148R-02 8.928z-03 3.0323-04 1.2603-04 4.7518-03 1.9753-03 8.8381-os 3.674B-05 8.793Z-05 3.6551-05 XB133M 1.381z-01 5.7503-02 1.698E-03 7.0723-04 4.6938-02 1.9548-02 B.il43-04 3.462R-04 8.3751-04 3.4883-04 XE133 3.391E+00 1.4113E00 2.770Z-02 1.1533-02 5.454E-01 2.2693-01 1.379X-02 5.7363-03 1.424B-02 5.9263-03 XZ135M 2.3401-02 1.0053-02 1.5253-03 6.552E-04 1.171Z-02 5.030R-03 1.0793-03 4.634E-04 1.0798-03 4.6343-04 X3135 2.253s+00 9.4783-01 2.3343-02 9.8193-03 9.53SE-01 4.011B-01 1.6643-02 7.0003-03 1.C670-02 7.059B-03 X1138 9.183E-31 7.s353-31 1.789z-32 1.468R-32 4.4853-31 3.680X-31 1.3743-32 1.128Z-32 1.374E-32 1.1283-32 C8135 8.3031-12 2.0283-12 .0003.00 .000Z+00 8.372E-13 2.0451-13 .0003+00 .000Z00 .0003+00 .OOO300 C8138 1.6513-30 5.611B-31 3.8383-32 1.30S1-32 8.716R-31 2.9631-31 2.9442-32 1.001-32 2.94Z1-32 1.001Z-32

A A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by, John N.Hamawi Page 58 ELZSA-2 LICNSING A SEVERE ACCIDIWS RADrOLOGICAL 1VALUATIONS - ENTECH ZNG. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAGE 18 CASE# 1 PUPS AST - VIA - BOUNDING SRC - 24 RR DECAY - RD VENT RZLEASES - CR - 1000 CYN (INSTANTANKOUS RZLZASE FROM SOURCE)

T - 5.0000z-01 bra EXTERNAL RADIATXON EXPOSURt DUE TO AIR8ORN8 RAD!OACT=VITY (CONTINUOUS OCCUPANCY)

COMPARTMENT C (INTERVAL DOSES ARE FROM .00001i00 TO 5.OOOOE-01 brs)

Beta Air Beta Air Gamea Air Ga=a Air Tot. Skin Tot. Skin Gonads Gonads Breast Breast DOSs RATE INSVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE rNTVL DOS DOSE RATE INTVL DOS (rad/hr) (rad) (rad/hr) (rad) (rem/br) (rem/br) (rem) (rem/hr) (rem)

GROUP 1 6.028E+00 2.520K+00 5.555Z-02 2.326R-02 1.6431+00 6.883R-01 3.395S-02 1.423Z-02 3.98SZ-02 1.6701-02 GROUP 2 4.568B-02 1.910B-02 1.212Z-03 5.073E-04 1.9441-02 8.1338-03 8.5941-04 3.5983-04 9.8181-04 4.1113-04 GROUP 3 4.786B-02 1.399Z-02 1.6641-04 4.8631-05 2.5618-02 7.4841-03 1.293E-04 3.778Z-05 1.4551-04 4.2531-05 GRND.TOT 6.122E+00 2.5531+00 5.693Z-02 2.3828-02 1.6881+00 7.039Z-01 3.494E-02 1.463B-02 40*098s-02 1.7152-02 CUM. TOTAL FROM T.0 2.5531+00 2.3828-02 7.039B-01 1.4631-02 1.715B-02 Lungs Lungs R.Marrow R.Marrow lone our Done Bur Thyroid Thyroid Rp-aindr Remainidr DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS WDO8 RATE .INTVL DOS DOW8 RATE ITNTVL DOS (rem/hr) (rem) (rem/hr) (rem) (rem/br) (rem) (rem/br) (rem) (rem/hr) (rem)

GROUP 1 3.0558-02 1.281Z-02 2.7301-02 1.145E-02 B.837B-02 3.698Z-02 3.317i-02 1.391Z-02 2.901B-02 1.217Z-02 GROUP 2 8.554Z-04 3.5828-04 8.2661-04 3.4611-04 1.510B-03 6.3171-04 8.7751-04 3.674E-04 8.161B-04 3.417Z-04 GROUP 3 1.3139-O0 3.836Z-OS 1.3093-04 3.8241-05 1.8321-04 5.3541-05 1.3371-04 3.906E-05 1.273E-04 3.720B-05 GRND.TOT 3.1538-02 1.3211-02 2.825Z-02 1.184E-02 9.006Z-02 3.7671-02 3.418E-02 1.4311-02 2.996Z-02 1.255-02 CUM. TOTAL FROM TaO 1.321Z-02 1.184B-02 3.7671-02 1.4311-02 1.2551-02 Bff D.C. 8ff D.E. TID Thy TID Thy RG11O9WB R011O9WB DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOS RATE INTVL DOS (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 3.377Z-02 1.416E-02 .000H+00 .0003+00 5.000Z-02 2.094B-02 GROUP 2 8.8021-04 3.685E-04 .0001E00 .000N.00 1.1381-03 4.7653-04 GROUP 3 1.333Z-04 3.8941-03 .0001.00 .0001+00 .0001+00 .0001+00 ORND.TOT 3.478B-02 1.45G6-02 . 000100 .000.+00 5.1141-02 2.1421-02 CuM. TOTAL FROM TaO 1.4561-02 .000+0O0 2.1421-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 59 ARE VA BLISA-2 [LICENSINO & SEVERE ACCIDENT RADIOLOGICAL 3VALUATIONB - ENTECK BNO. - Rol. Version 2.2 May 23,20021 28-Oet-04 PAGE 19 CAS8B 1 PNPS AST - FHA - BOUNDINO 8RC - 24 HR DECAY - RB VENT RELASE9 - CR - 1000 CFM (INSTANTANEOUS RELEASE PROM SOURCE)

T - 5.0000Z-01 bra RADIATION EXPOSURE DUZ TO INHALATION (CONTINUOUS OCCUPANCY)

COMPARTMENT C (INTERVAL DOS8 ARE FROM .00001400 TO 5.00003-01 bra)

Thyroid Thyroid Zff D.E. 8ff D.E.

DOSE RATE INTVL DOS DOSE RATS INTVL DOS NUCLIDS (rem/hr) (rem) (rca/hr) (rem)

BR 82 2.5993-04 1.0853-04 5.2103-04 2.175-04 BR 83 2.397B-08 1.059B-08 5.067B-07 2.240E-07 BR 84 1.7918-18 9.9083-19 1.498Z-17 8.2883-18 KR 83M .000X+00 .0003+00 .000o+00 .0003+00 KR 85N .0005+00 .0003+00 .0005+00 .000E+00 KR 85 .0003+00 .000.E00 .0005+00 .0003+00 KR 87 .000X+00 .00oz+00 .0005+00 KR 88 .0003+00 .0003+00 .000E+00 RB 87 2.6053-20 6.590Z-21 3.180Z-20 8.0443-21 RS 88 8.320Z-05 2.4313-05 1.372E-03 4.0113-04 X128 5.895B-22 3.5433-22 1.4133-22 8.492E-23 I129 2.7923-05 1.161Z-05 8.3943-07 3.490E-07 1130M .0003+00 .oooe+00 .00O+00 .000E+00 1130 6.982E-02 2.937B-02 2.505Z-03 1.054E-03 1131 7.2523+01 3.0183+01 2.2083+00 9.188Z-01 1132 2.6023-04 1.153B-04 1.5403-05 6.824E-06 1133 7.3273.00 3.0688+00 2.382E-01 9.973B-02 1134 4.239Z-10 2.088Z-10 5.226B-11 2.574E-11 1135 2.059B-01 8.752B-02 8.0813-03 3.435R-03 XB131M .0003+00 .000X+00 .0003+00 .00O0300 XZ133N .000Z+00 .0003+00 .0003+00 .0003+00 XE133 .0003+00 .000E+00 .0003+00 .0003+00 XZ135M .0003+00 .0003+00 .000Z+00 .0000+oo Xl135 .000Z+00 .000E+00 .0003+00 .0003.00 XE138 .0003+00 .0003+00 .000Z+00 .0003+00 CS135 3.881R-10 9.4813-11 3.9783-10 9.718E-11 CS138 1.26CE-32 4.351B-33 9.8223-32 3.339E-32

.e

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWQ Prepared by- John N.Hamawi Document ID32-5052589-01 Page 60 AR EVA EL!SA-2 [LICMNSING & SEVERE ACCIDENT RADIOLoGicAL EVALUATIONS - ENTzcn ENG. - Rel. Verulon 2.2 May 23,20021 28-Oct-04 PAGE 20 CASE# 1 PNPS AST - MIA - BOUNDING SRC - 24 RR DECAY - RB VENT RELEASES - CR - 1000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

T N S.0000B-01 hra RADIATION ExPOsURE DUE TO INHALATION (CONTINUOUS OCCUPANCY)

COMPARTMENT C (INTERVAL DOSES ARE FROM .00003E00 TO 5.0000B-01 br.)

Gouada Gonada Breast 8reaut DOSE RATE INTVL DOs DOSE RATE INTVL DOS (rem/hr) (re=) (rem/hr) (rem)

GROUP I . 000o00 .000E+00 .0001+00 .0003E00 GROUP 2 9.9S13-03 4.153e-03 2.501X-02 1.043E-02 GROUP 3 7.9553-05 2.3253-05 8.6843-05 2.53se-05 GRND.TOT 1.0031-02 4.1763-03 2.5101-02 1.0453-02 CUM. TOTAL FROM T-O 4.176Z-03 1.045E-02 Lungs Lunga R.Marrow R.Marrow Bone our Done Bur Thyroid Thyroid Remwandr Ramaindr DOSE RATE INTVL DOS DOSE RATE rNTVL DOS. DOSE.RATR INTvL DOB DO8E RATE nTV. DOS DOSE RATE INTVL DOS (rem/hr) (rem) (rem/br) (rem) (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 .0003.00 .0003+00 .000.E00 .0001+00 .0001+00 .OOO+00 .OOO+00 .0003+00 .000Z+00 .0003.00 GROUP 2 3.018B-01 1.2601-01 2.063B-02 8.601E-03 1.8913-02 7.882B-03 8.0133+01 3.3363+01 2.9333-02 1.2248-02 GROUP 3 8.9273-03 2.609B-03 8.8063-05 2.5738-05 .s9273-05 2.609E-05 8.3203-05 2.4313-05 8.3911-04 2.4493-04 GRND.TOT 3.107B-01 1.28s6-01 2.0723-02 8.6273-03 1.8s9s-02 7.9081-03 8.0133+01 3.3361+01 3.017Y-02 1.2483-02 CUM. TOTAL FROM T.0 1.2986-01 8.627z-03 7.908B-03 3.3361+01 1.248Z-02 zff D.E. Bff D.E. TID Thy TID Thy I DOSE RATE INTVL DOS DOSE RATE INTVL DOS (rem/hr) (rem) (rem/hr) (remn)

GROUP 1 .0001+00 .000E+00 .0001+00 .000.+00 GROUP 2 2.457E+00 1.0233.00 1.1653+02 4.851+,01 GROUP 3 1. 372B-03 4.011E-04 .0ooo0 00 .0001+00 GRND.TOT 2.4591+00 1.0243+00 1.1653+02 4A.51B+01 CUN. TOTAL FROM TnO 1.0241+00 4. 9513+01

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Allemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-1 Page 61 AR EVA ELISA-2 [LICENSING A SEVERE ACCIDENT RADIOLOGICAL 3VALUATIONS - =N=ECH ENO. - Rol. Version 2.2 May 23.20021 28-Oct-04 PA.0 21 CASES 1 PNPS AST - PRA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - CR - 1000 CPM (INSTANTANEOUS RELEASE FROM SOURCE)

SUMM(ARY TOTAL RADIATION EXPOSURES (AIR IMMERSION PLUS INHALATIONh (CONTINUOUS OCCUPANCY)

COMPARTEENT C Beta Air Beta Air Beta Air Gsam Air Gamma Air Gamek Air Tot. Skin Tot. Skin Tot. Skin DOSE RATE SNTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INRVM DOS CUM. DOSE T (hours) (rad/hr) (red) (red) (red/hr) (red) (red) (rem/hr) (rem) (rem)

.00003+00 .000B+00 .000R+00 .0003+00 .000+00 .000B+00 .00O+00 .0003+00 .0003+00 .0003+00 5.0000B-01 6.122R+00 2.5533+00 2.5533+00 5.6933-02 2.382Z-02 2.3823-02 1.688R+00 7.039B-01 7.0398-01 1.00003+00 3.3683+00 2.3793+00 4.9323+00 3.1633-02 2.2183-02 4.6003-02 9.2783-01 6.555B-01 1.3593+00 2.00003+00 6.830Z-0l 1.6973+00 6.6283+00 7.1963-03 1.6423-02 6.2413-02 1.930Z-01 4.6973-01 1. 829E+00 8.0000z+00 2.9083-02 5.8733-01 7.2153+00 6.6123-04 8.6873-03 7. l103-02 1.136Z-02 1.8853-0Ol 2.018F+00 2.40003+01 2.6703-03 9.561Z-02 7.3113+00 4.917Z-05 1.9763-03 7.3093-02 8.690e-04 3.5163-02 2.0533+00 9.6000z+01 1.0543-04 4.10&4-02 7.3523+00 9.811B-07 5.7283-04 7.365E-02 1.939E-05 1.0538-02 2.0633+00 7.2000c+02 1.1273-06 5.0303-03 7.3573+00 1.591E-08 S.7793-05 7.371Z-02 2.493Z-07 1.009Z-03 2.064R+00 Gonadt Gonadn Gonads Breast Breast Breast Lungs Lungs Lungs DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CVM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00003+00 .OOO+00 .oooe+00 .0003+00 .000B+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 5.0000o-01 4.497Z-02 l.880Z-02 1.880B-02 6.6083-02 2.76O0-02 2.760B-02 3.423E-01 1.4183-01 1.4183-01 1.0000B+00 2.492E-02 1.751-02 3.631Z-02 3.6573-02 2.572E-02 5.332Z-02 1.8843-01 1.332B-01 2.751Z-01 2.00003+00 5.5373-03 1.285E-02 4.9163-02 7.8743-03 1.871E-02 7.2043-02 3.620B-02 9.3763-02 3.688E-01 8.0000e+00 4.5212-04 6.297E-03 5.5463-02 5.1963-04 8.0913-03 8.0133-02 4.4083-04 2.356E-02 3.9243-01 2.4000E+02 3.248E-05 1.337E-03 5.680E-02 3.7523-05 1.5373-03 8.1663-02 3.1043-OS 1.294E-03 3.937E-01 9.6000E+01 4.*884-07 3.5403-04 5.7153-02 5.9953-07 4.14&3-04 8.2089-02 3.8943-07 3.2599-04 3.940B-01 7.20003+02 5.4213-09 2.356E-05 5.717E-02 7.1423-09 2.9913-05 8.2113-02 3.167Z-09 1.6373-05 3.9403-01 R.Marrow R.Marrow R.Marrow Bone Sur Bone Sur Bone Sur Thyroid Thyroid Thyroid DOSE RATE INTVL DOS CVM. DOSE DOSE RATE INTV DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00003+00 .OOO+00 .OOO+00 .000Z.00 .0003+00 .0003+00 .OOOZ+00 .000+00 .0003+00 .0003+00 5.00008-01 4.897Z-02 2.047E-02 2.047E-02 1.091E-Ol 4.557B-02 4.5S78-02 8.0163+01 3.3383+02 3.3383+01 1.0000R+00 2.7113-02 1. 9063-02 3.9538-02 6.0323-02 4.2443-02 8.8013-02 4.4113+01 3.1173+01 6.4553+01

2. 0000E+00 S.9OOB-03 1.391E-02 5.344z-02 1.3003-02 3.087E-02 1.189B-01 8.4173.00 2.195E+01 8.6503+01 8.00003+00 4.194E-04 6.2833-03 5.972Z-02 8.8003-04 1.35OB-02 1.3243-01 6.821Z-04 4.8163+00 9.1323+01 2.40003+01 2.920o-os 1.2288-03 6.0953-02 6.73&4-05 2.6643-03 1.3503-01 3.261B-05 1.4773-03 9.1323+01 9.60003+01 3.2383-07 2. 9853-04 6.1253-02 1.4403-06 8.165B-04 1.3598-01

4.552B-07 3.4963-04 9.132Z+01 7.2000E+02 2.6933-09 1.3713-05 6.126Z-02 1.2573-08 6.269Z-05 1.359B-01 4. 6393-09 2.1093-05 9.132E+01

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 62 AR EVA ZLISA-2 (LICENSING & SEVERE ACCIDZNT RADIOLOGICAL ZVALUATIONS - EZNTCH BNO. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 22 CASR# 1 PNPS AST - PEA - ROUNDING SRC - 24 HR DECAY - RD VZNT RELEASES - CR - 1000 CPX (INSTANTANEOUS RELEASE FROM SOURCB)

SUMSMARY TOTAL RADIATION EXPOSURES (AIR IMBRSION PLUS UNHALATION) (CONTINUOUS OCCUPANCY)

COMPART11ENT C Remaindr Rem-indr Remaindr 3ff D.H. Eff D.E. 3ff D.E. TID Thy TID Thy TID Thy DOSE RATE ImTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSB S (hours) (re=/Ur) (rem) (re) (rem/br) (rem) (rem) (rem/hr) (rem) (rem)

. 00003+00 . oOO+OO .OOO+00 . 0003Z00 .0003+00 . 000300 .0003+00 .000Z+00 .0003+00 .0003+00 5.00003-01 6.013B-02 2.503Z-02 2.503B-02 2.4933.00 1.0383400 1.0389+00 1.1653+02 4.8513.01 4.851z+01 1.0000B+00 3.329Z-02 2.3423-02 4.845E-02 1.372R300 9.697Z-01 2.0083+00 6.4033.01 4.5273+01 9.378O+40 2.0000Z+00 7.052E-03 1.696s-02 6.5415-03 2.626Z-01 9.833E-01 2.69 1+00 1.2203+01 3.1843+01 1.2563+02 8.0000x+00 4.2001-04 6.934N-03 7.235B-02 4.662B-04 1.5333-01 2.8443+00 3.2253-04 6.9663+00 1.3263+02 2.4000z+01 2.959Z-05 1.2343-03 7.3585-02 3.2823-05 1.3608-03 2.8463+00 1.9981-16 1. 8353-04 1.3263+o2 9.60003+01 3.6903-07 3.101B-04 7.3099-02 4.6663-07 3.536N-04 2.8463+00 2.6703-71 1.138Z-16 1.3263+02 7.20003.02 3.215Z-09 1.5973-OS 7.391E-02 4.6153-09 2.133B-05 2.8463+00 .oooe000 1.5273-71 1.3261+02 RO1109W3 RO1109W3 RO1109WB DOSE RATE NTVZL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem)

.OOOO+.00 .0003+00 . 000+00 .0003+00 5.00003-01 5. 114-02 2.142B-02 2.142E-02 1.00003+00 2.8403-02 1.992Z-02 4.1343-02 2.00003+00 6.496E-03 1.4763-02 5.610B-02 8.00003+00 6.1283-04 7.958z-03 6.4053-02 2.40003+01 4.4963-05 1.6243-03 6.583Z-02 9.60003+01 7.6153-07 5.0813-04 6.6393-02 7.20003+02 6.6413-09 3.305Z-05 6.642B-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 63 AREVA ELISA-2 [LICENSING & SEVERN ACCID3NT RADIOLOGICAL EVALUATIONS - ENTECH MNM. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAOG 23 CASE# 1 PNPS AST - FMA - BOUNDING 8RC - 24 UR DECAY - RB VENT RELEASES - CR - 1000 CFN (INSTANSANEOUS RELSA8S FROM SOURCE)

OVERALL SUMARY - TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR SCENARIO DURATION (7.20001+02 bra)

CONTINUOUS OCCUPANCY RECEPTOR/ORGAN COMPARTMENT A COMPARTMS N B COMPARTMENT C OFFBITS RZCEP.

(Remispher) (Spherical) (lnemispher)

Beta Air (rad) .0003.00 .000E+00 7.3578+00 .0001z00 Gm-a Air (rad) .0001+00 .0008+00 7.3711-02 .0001+00 Tot. skin (rem) .000Z+00 .000B+00 2.0641+00 .0001+00 IBeta Cont. Mt)) C .001 I .001 1 97.251 I .001 Gonads (rem) .0008+00 .0001.00 5.7171-02 .0001+00 Breast (rem) .000H+00 .0001+00 8.2113-02 .0001+00 Lungs (rem) .000B+00 .0001+00 3.9401-01 .0003+00

[Inhalation pi)I 1 .001 I .00] 1 89.411 I .001 R.Karrow (rem) .000+00 .000+00 6.1263-02 .0003+00 Bone Sur (rem) .000.+00 .0008+00 1.359e-01 .000B+00 Thyroid (rem) .000E+00 .OOOE+00 9.132E+01 .0003+00 CInhalation ") I I .001 1 .001 C 99.951 I .001 Remaindr (rem) .0003+00 .oooe+00 7.391Z-02 .0008+00 Eff D.E. (rem) .0001400 ooe000 2.8461+00 .000+00 (Inhalation (%)] 1 .001 .001 C 90.391 I .001 TID Thy (rem) .000R+00 .0008+00 1.326E+02 .OOO+00 R0l1O9WB (rem) .000E+00 .000B+00 6.6423-02 .000E+00 The Done Conversion Factors (DCFs) employed by BLIBA-2 are from EPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for TID Thy and RO1109WB, which are as followns TID Thy = Classical thyroid inhalation dose based on the TID-14844 DCUe (iodine. only)

RO109WB

Classical whole body immersion dose based on the Reg. Guide 1.109 DCrs (nobles and halogens only)

The beta dose to air in for irersion in an Infinite cloud.

The skin dose includes contributions from gamca radiation (finite cloud), beta radiation (semi-infinite cloud) and ground contamination. The skin beta-contribution percentages exclude ground contamination.

Finlte-cloud correction, if any, is nuclide specific.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWQ)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 64 AR EVA ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENT CH ENG. - Rel. Version 2.2 May 23,20021 28-Oct-04 PACE 24 CASE# I PNPS AST - IRA - BOUNDING SRC - 24 MR DECAY - RB VENT RELEASES - CR - 1000 CFM (XNSTANTANEOUS RELEASE FROM SOURCE)

SUKMARY TOTAL RADIATION EXPOSURES (AIR IXMERSION PLUS INEALATION) (PARTIAL OCCUPANCY)

COMPARTMENT C Beta Air Beta Air Beta Air GOn-a Air Gamma Air Gamna Air Tot. Skin Tot. Skin Tot. Skin DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rad/hr) (rad) (rad) (rad/hr) (rad) (rad) (rem/hr) (rem) (re=)

.*0000+00 .0003400 .0003+00 .0003.00 .OOO+00 .000E+00 .0003+00 .000E+00 .0003+00 .0003+00 5.0000z-01 6.122H400 2.*553300 2.5533+00 5.693Z-02 2.382E-02 2.3823-02 1.6883z00 7.039B-01 7.039E-01 1.00003+00 3.3683.00 2.3793+00 4.932E+00 3.163E-02 2.2183-02 4.600B-02 9.2783-01 6.S55B-01 1.3593.00

2. 00003+00 6.830B-01 1.697E+00 6.6283+00 7.196B-03 1.642Z-02 6.2413-02 1.930B-01 4,697Z-0O 1. 8293.00 8.00003+00 2.908Z-02 5.873E-01 7.2153+00 6.612E-04 8.6878-03 7.1103-02 1.136B-02 1.a85-01 2.0183+00 2.40003+.0 2.670B-03 9.561B-02 7.3113.00 4.917Z-05 1. 9763-03 7.3083-02 8.0690Z-04 3.5163-02 2.0533+00

9. 60003+01 1.0543-04 4.1043-02 7.3523,00 9.811B-07 5.7283-04 7.3653-02 1.939Z-05 6.350-03 2.0593+00 7.2000z+02 1.127Z-06 5.030B-03 7.3573+00 1.591B-08 5.7793-05 7.3713-02 2.493B-07 4.0358-04 2.0593+00 Gonads Gonads Gonads Breast Breast Breast Lungs Lungs Lungs DOSE RATE NTVL DOS CUM. DOSE DOSE RATE rNTVL DOS CBM. DOSE DOSE RATE INTVL DOS CUM. DOSE S (hours) (rem/hr) (rea) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00003+00 .0003+00 .0003,00 .OOOZ300 .0003+00 .0003+00 . 000E.00 .0003+00 .000B00 .OOO+00 5.0000E-01 4.497E-02 1.880Z-02 1.880E-02 6.608Z-02 2.7603-02 2.760E-02 3.4233-01 1.418z-01 1.418Z-01 1.0 000E+00 2.492E-02 1.751Z-02 3.6313-02 3.657Z-02 2.5723-02 5.3323-02 1.8843-01 1.3323-01 2.751Z-01 2.00003+00 5.537B-03 1.285Z-02 4.916B-02 7.874E-03 1.871E-02 7.2043-02 3.620B-02 9.376B-02 3.688E-01 8.00003+00 4.521E-04 6.2973-03 5.546B-02 5.186B-04 8.0913-03 8.0133-02 .4.408B-04 2.356B-02 3.9243-01 2.40003+01 3.248E-05 1.337Z-03 5.6803-02 3.752E-0S 1.5373-03 8.1663-02 3. 104E-05 1.2943-03 3.9373-01 9.60003+01 4.9843-07 2.124B-04 5.701B-02 5.985E-07 2.4873-04 8.191Z-02 3.8943-07 1.9553-04 3.9393-01 7.20003+02 5.421-09 9.4243-06 5.7023-02 7.142E-09 1.1978-05 8.1923-02 3.167B-09 6.5473-06 3.939Z-0O R.Marrow R.Karrow R.Marrow Bone Sur Bono Sur Bone Bur Thyroid Thyroid Thyroid DOSE RATE INTVL DOS CUM. DOSE DOSE RATE rNTVL DOS CUM. DOSE DOSZ RATE INtVL DOS CVM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00003+00 . 000+00 .0003+00 .0003+00 .0003.00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00

5. 0000-0O1 4.897B-02 2.047Z-02 2.047P-02 1. 091B-01 4.557E-02 4.557B-02 8.0163+01 3.3383+01 3.3383+01 1.0000E+00 2.711Z-02 1.906B-02 3.953E-02 6.032Z-02 4.2443-02 8.8013-02 4.4113+01 3.1173+01 6.4553+01 2.00002+00 5.900B-03 1.391Z-02 5.3443-02 1.300Z-02 3.087Z-02 1.189Z-01 8.4173+00 2.1953+01 8.6503+01 8.00003+00 4. 1943-04 6.2833-03 5.9721-02 8.8003-04 1.350-02 1.3243-01 6.8213-04 4.8163+00 9.1323+01 2.40003+01 2.9203-05 1.228Z-03 6.0953-02 6.7343-05 2.6643-03 1.3503-01 3.2613-05 1.477B-03 9.1323+02 9.60003+01 3.238Z-07 1.7913-04 6.1133-02 1.440*-06 4.899E-04 1.355B-01 4.552B-07 2.097B-04 9.1323+01 7.20003+02 2.693B-09 5.482E-06 6.113E-02 1.2573-08 2.508Z-05 1.356E-01 4.639E-09 8. 435B-06 9.1323+01

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by' John N.Hamawi Document ID32-5052589-01 Page 65 AR EVA ZLISA-2 tLC*NSrIN a SEVER. ACCIDENT RADIOLOGICAL EVALUATIONS - ENTICE ZNO. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGE 25 CASE 1 PNPS AST - FYA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - CR - 1000 CRn (INSTANTANEOUS RELEASE FROM SOURCE)

SUMMARY

TOTAL RADIATION HIPOSURES (AIR IM1IRBION PLUS INXALATION) (PARTIAL OCCUPANCY)

COMPARTMENT C Remilndr Re-aIndr Remaindr Bff D.E. Zff D.E. 3ff D.E. TID Thy TID Thy TID Thy DOSE RATE INTVL DOS CUM . DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hourn) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (ram) (rem)

. ooooe+00 .000+.00 .0003+00 .O000O00 .000x+OO .0003.+00 .0001+OO .0003+00 .0003.00 .OOO+00 5.0000R-01 6.013B-02 2.503Z-02 2.5033-02 2.493+.00 1.0385+00 1.0383+00 1.1653+02 4.851+401 4.8513401 1.00003+00 3.329R-02 2.3423-02 4.8453-02 1.372+.00 9.697Z-01 2.008B+00 6.4033+01 4.5273+01 9.3783+01 2.00001+00 7.052R-03 1.696R-02 6.541R-02 2.626R-01 6.8333-01 2.6913+00 1.2203+01 3. 1841.01 1.2563+02 8.0000X.00 4.200E-04 6.934B-03 7.235B-02 4.6623-04 1.533Z-01 2.8443+00 3.225S-04 6.966Z+00 1.3261+02 2.40003+01 2.959R-05 1.234R-03 7.358B-02 3.282E-05 1.360R-03 2.8461+00 1.998B-16 1.8353-04 1.3261+02 9.60001+01 3.698Z-07 1.86CR-04 7.3773-02 4.6663-07 2.122B-04 2.8463+00 2.6783-71 6.8271-17 1.3261+02 7.20003+02 3.215E-09 6.387B-06 7.377B-02 4*.615B-09 8.5333-06 2.846E.00 .0001.00 6.107Z-72 1.3263.02 RTOG19WB RGIXO9Wa R01109WB DOSE RATE INTYv DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem)

.00003+00 .0003+00 .000X*00 .OOO+00 5.0000-01 5.114Z-02 2.1423-02 2.1423-02 1.00003+00 2.8403-02 1.992B-02 4.1343-02 2.0000E+00 6.496Z-03 1.4763-02 5.6103-02 8.00003+00 6.1281-04 7.9583-03 6.405B-02 2.40003+01 4.4963-05 1.8241-03 6.5883-02 9.60003+01 7.6153-07 3.048B-04 6.6183-02 7.2000E*02 6.641E-09 1.322B-05 6.620Z-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source TemmMethodology (2038 MWI)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 66 ELISA-2 CLICENSINO SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECE MMG. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 26 CASEZ 1 PNPS AST - FRA - BOtNDINO SRC - 24 BR DECAY - RD VENT RELEASES - CR - 1000 Cr1 (INSTANTANEOUS RELEASE FROM SOURCE)

OVERALL

SUMMARY

- TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR SCENARIO DURATION (7.2000Z-02 bra)

PARTIAL OCCUPANCY RECEPTOR/ORGAN COMPARTMENT A COMPARTMENT B COMPARTMENT C OFFSITE RECEP.

(Hemispher) (Spherical) (Hemispher)

Beta Air trnd) .0003+00 .000Z+00 7.357Z+00 .000B+00 Oa^na Air (rad) .0008+00 .000Z+00 7.371Z-02 .000Z+00 Tot. skin (rem) .0001+00 .000Z+00 2.059Z+00 .0001+00 (Beta Cont. (%)] I .003 1 .00) 1 97.251 C .003 Gonads (rem) .000H+00 .000Z+00 5.7023-02 .0001+00 Breast (rem) .000E-00 .0003+00 8.192E-02 .0008+00 Lungs (rae) .O00R+00 .0001+00 3.9398-01 .000Z+00 (Inhalation (%)] I .001 C .001 t 89.441 C .001 R.Marrow (rem) .0001+00 .000Z+00 6.113z-02 .000Z+00 Bone Sur (rem) .000B+00 .000Z+00 1.356Z-01 .0008+00 Thyroid (rem) .000Z+00 .000Z+00 9.1328+01 .000B+00

[Inhalation 1 I%)1 .00] t .00) C 99.95) C .001 Rezaindr (rem) .000Z+00 .0001+00 7.377B-02 .00o0+00 Zff D.E. (rem) .000Z+00 .000Z+00 2.8461.00 .0001+00 (Inhalation (%)] r .00) I .001 t 98.40] C .00)

TID Thy (rem) .0001.00 .000Z+00 1.326B+02 .000B+00 RG1109WB (rem) .000B+00 .000Z+00 6.620B-02 .000Z+00 The Dose Conversion Factors (DCFs) employed by SLISA-2 are from SPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for TID Thy and R01109WB, which are as followns TID Thy n Classical thyroid Inhalation dose based On the TID-14844 DCrs (iodine. only)

RO1109WB - Classical whole body lmrsion done basoed on the Rog. Guide 1.109 DC~s (nobles and halogens only)

The beta dose to air is for lmeralon in an infinite cloud.

The skin dose includes contributions from gaea radiation (finite cloud), beta radiation (semi-infinite cloud) and ground contamination. The skin beta-contribution percentages exclude ground contamination.

Finite-cloud correction, if any, Is nuclide specific.

Partial occupancy hae been applied only to human exposures in Compartment C.

- - - - ZND OF THIS CASE **-

A A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 AR EVA Prepared by: John N.Hamawi Page 67 BLISA-2 ILICNSINO a SEzvEE ACcIDENT RADIOLOGIcAL EVALUATIONS - ZNZECR ENa. - Rol. VoraIon 2.2 May 23,20021 28-Oct-04 PA.E 27 CASE# 2 PNPS AST - YA - BOUNDINO SRC - 24 RR DECAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

LISTING OF INPUT DATA PATHWAY OPTION n 4 (COMP. A -- > COMP. C)

COMPARTMENT As Refueling Level TOTAL FREE AIR VOLUME (cu ft) D 7.0001+05 FILTERED RECIRCULATION RATE (cfm) - .0001+00 LEAK RATE TO ATMOSPHERE (frac/day) n 9.600H+01 COMPARTMENT Ct Control Room TOTAL FREE AIR VOLUMM (cu ft)

3.4281+04 INTAXKE AND M[HAUST RATES (cfm)

9.0001.03 FILTERED RECIRCULATION RATE (cfrn) * .0001+00 FILTER REMOVAL EFFICIENCIES AND TISM-DEPENDENT MULTIPLIERS FOR RRCIRCULATION RATES, LEAK RATES, COMP. A FLOW BETWEEN SPRAYED AND UNSPRAYED AREAS, AND FILTER BYPASS FRACTIONS ARE OIVEN BELOW.

NO. OF DISCRETE TIME VALUES IN INPUT

8 INTERMEDIATE RESULTS WILL BE PRINTED AT TER FOLLOWING TIMES (Mrs)s

. OOOOE+00 PROBLEM END TIME (hours)- 7.20001+02 RELEASE RATES AND DOSE RATES ARE PRIOR TO TINX-STEP CHANGES, IF ANY.

ONLY EXACT SOLUTION OF THE DIFFERENTSAL zQuATIONS WAS EmPLOYED iN THE ANALYSIS.

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 68 BLISA-2 tLICZNSING a SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECR ENG. - Rol. Vernion 2.2 Nay 23,2002] 28-Oct-04 PAGE 28 CASB 2 PNPS AST - YrA - BOuNDINO SReC - 24 nR DECAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELZASE FROM SOURCE)

RECIRCULATION, ZXRAUSS AND INTAXE FILTER REMOVAL EFFICIENCIES (fractioni)

CONPAMSMENT A FBCTRC. COMPAR~mN B RZCIRC. COMPARTMENT C RECIRC. EXRAUST TO ATMOSPHERE INTAKE TO COMPART. C NUCL.

GROUP FORM 1 FORM 2 FORM 3 FORM 1 FORM 2 FORM 3 FORM 1 FORM 2 YORN 3 FORK 1 FORM 2 FORM 3 FORM 1 FORM 2 FORM 3 1 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 2 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 3 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 USER-SPECIFIED CLASSIFICATION OP RADIONUCLIDES AND INSTANTANEOUS FRACTIONAL FELEABES FROM THE SOURCE (AT TaO)

GROUP Z L Z N Z N T S FORM 1 FORM 2 FORM 3 1 KR XE 1. 000S00 . 0003+00 .OOO+00 2 BR I 2.850-03 2.150E-03 .OOOE+00 3 ZZ .000Z+00 .0003+00 .000oe00 ELEMENT ZZ' STANDS FOR THe REMAINING DATA-LIBRARY ELENENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

AA PNPS Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Termn Methodology (2038 MWt)

Document ID32-5052589-01 A R E VAt Prepared by: John N.Hamawi Page 69 BLISA-2 ILICNSIN & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTICE ZEa. - Rol. Vernion 2.2 May 23,2002] 28-Oct-04 PAGE 29 CASES 2 PNPS AST - PHA - BOUNDING SRC - 24 MR DBCAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELEASE PROM SOURCE)

TIME INTERVAL CONCENTR. GAMMA DEPOSITION BREATNnnG EI.PFILT. COMPART. C COMPART. C X/Q X/Q D/Q RATE BYPASS IN?.FILTZR OCCUPANCY (bourn) (sec/=3) (sec/m3) (1/=2) (m3/sec) FRACTION BYPASS FR. FACTOR

.OOOOE00 - 5.0000Z-01 1.760-03 1.760B-03 .0001+00 3.5003-04 .000R+00 .0001+00 1.0001.00 5.0000B-01 - 1.00001.00 1.760Z-03 1.7601-03 .000B+00 3.5001-04 , .OOOE+00 .0001+00 1.0001+40 1.0000X+00 - 2.0000E+00 1.760Z-03 1.7601-03 .0001+00 3.500X-04 .0008+00 . 0001+00 1.0001+00 2.00001E00 - 8.00001+00 1.250B-03 1.250Z-03 .0001.00 3.5001-04 .OOOE+00 . OOO+.00 1.000+00 8.0000+00 - 2.4000Z+01 4.2601-04 4.2601-04 .000z+00 3. 5001-04 * .0001+00 .0001+00 1.0001.00 2.40001.01 - 9.60001+01 3.670Z-04 3.670B-04 .0oooz00 3.5001-04 .00o0+00 .000oo00 6 *0001-01 9.60001+01 - 7.2000E+02 3.15OE-04 3.1501-04 .000x+00 3.5001-04 .0001.00 .0001+00 4. 0001-01 TIME INTERVAL COMPART A MULTIPLIERS COMPART B MULTIPLIERS COMPART C MULTIPLIERS FLOW MULT.

(IF APPLICABLE) (IF APPLICABLE) (Ir APPLICABLE) SPRAYED AREA (hours) LEAK RATE , REC.PILTZR LEMA RATE REC.FILTzR INTPA 4 E/IX RXC.FILTER TO UNSPRAYED

.000o0+00 - 5.0000Eo-0 1.0001+00 1.000o+00 1. 0001+00 1.0001+00 1.*000+00 1. 000+00 1.000Z+00 5.00001 1.0000Z+00 1.0001+00 1. 0001E00 1.0001+00 1. 0001+00 1.0001+00 1. 0001Z00 1.0001+00 1.0000+.00 - 2.0000H+00 1.000E+00 1. 0001+00 1.0001+00 1.000R+00 1.0001+00 1. 0001+00 1. 000+00 2.00001+00 - 8.0000E+00 1.000z+00 1.0001+00 1.0001+00 1. 000Z+00 1.0001+00 1. 000+E00 1. 000+00

.o0000z+00 - 2.40001+01 1. 000+00 1. 0001.00 1.000o+00 1.0001+00 1. 000100 1.0001+00 1 000E+00 2.40001+01 - 9.60001.01 1.0001+00 1. 0001+00 1.0001+00 1.0001+00 1.000B+00 1 *000Z+00 1.0001+00 9.66000+01 - 7.2000Z+02 1.000E+00 1. 000+00 1. 0001+00 1. 000+00 1.000X+00 1.000Z+00 1. 0001+00

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 70 AR EVA ELISA-2 (rICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH MEG. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 30 CASE# 2 PNPS AST - PEA - BOUNDING 8RC - 24 RR DECAY - RB VENT RELEASES - CR - 9000 CFP (INSTANTANEOUS RELEASE FROM SOURCE)

USER-SPECIFIED SOURCE INVENTORY NUCLIDE GROUP (CL) NUCLIDE GROUP (Ci) NUCLIDE GROUP (Ci)

BR 82M 2 7.89203+01 KR 87 1 1. 1750E+04 1134 2 3.81503+04 BR 82 2 2.04203+02 KR s8 1 1.66203+04 1135 2 3.18203+04 BR 83 2 2.5670E+03 FR 89 1 2.09603+04 1136H. 2 9.44603+03 BR 84M 2 1.3280E+02 KR 90 1 2.08103+04 1136 2 1.54403+04 BR 84 2 4.7330z+03 1128 2 5.70203+02 XZ131M 1 1.90503+02 BR 05 2 5.8150R+03 1129 2 1.7930K-03 XR133M 1 1.05203+03 BR 86 2 4.35603+03 1130M 2 5.40203+02 XE133 1 3.41703+04 BR 87 2 9.92103+03 I130 2 1.38303+03 XE135M 1 6.82503+03 BR 88 2 1.13003404 X131 2 2.7170R+04 XZ135 1 1.74403+04 KR 83M I 2.56703+03 X132 2 2.41103+04 Xe137 1 3.00703+04 KR 85M 1 5.88003+03 X133 2 3.4170R+04 XE138 I 3.03703+04 KR 85 I. 8.5510E+02 11343 2 4.07403.03 XZ139 I 2.4470E+04 EL$SA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTEC ENm. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 31 CASE# 2 PNPS AST - MMA - BOUNDING 5RC - 24 RR DECAY - RB VENT RELBASES - CR - 9000 CFH (INSTANTANEOUS RELEASE FROM SOURCE)

SOURCE INVENTORY FOLLOWING 2.4003+01 fOURS OF RADIOACTIVE GROWMT AND DECAY PRIOR TO RELEASE NUCLIDB GROUP (C1) NUCLIDR GROUP (CL) NUCLIDE GROUP (CL)

BR 82 2 1.27613+02 SR 09 3 9.0150Z-01 X1333M 1 9.4669+.02 BR 83 2 2.43523+00 1128 2 2.54193-15 X3133 1 3.28693+04 BR 84 2 1.1057B-10 1129 2 1.79303-03 X3135M 1 4.11603+02 KR 83M 1 9.44453+00 S130M 2 3.69633-46 X3135 1 9.60503+03 KR 85M 1 1.45053+02 1130 2 3.61473+02 X8138 1 7.77763-27 FR 85 1 8.55013+02 1131 2 2.49263.04 C8135 3 6.6014E-06 RR 87 1 2.47292-02 1132 2 1.74193+01 CS137 3 7.29873-03 KR 88 1 4.74433+01 1133 2 1.53573+04 C8138 3 8.23373-10 RB 87 3 3.6297R-11 1134 2 .2.18963-04 CS139 3 1.41353-43 RB 88 3 5.2925E+01 1135 2 2.5697E+03 BA137M 3 6.9045X-03 RB 89 3 1.6731E-25 S8131M 1 1.96063+02 BA139 3 1.27003-03

ABasedA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32.5052589-01 A R EVA Prepared by: John N.Hamawi Page 71 NLISA-2 rLICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH ING. - Rol. Veruion 2.2 May 23,20023 28-Oct-04 PAGE 32 CASE# 2 PUPS AST - mRA - BOUNDING SRC - 24 RR DECAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANZOUS RELZASB FROM SOURCE)

T a .00003+00 hr. DISTRIBUTION OF RADIOACTIVITY NUCLIDE COMPARTM. CREM-SPRAY REC.7FLTER COMPARTH. REC.FILTER 3X2.PILTER COMPARTM. INT.FILTZR REC.FILTSR A IN COMP. A IN COMP. A B IN COMP. B TO ATMOSU. C TO COMP. C IN COMP. C (CL/m3) (CL) (Ci) (ci/=3) (Ci) (Ci) (Ci/=3) (Ci) (CI)

HR 82 3.219Z-05 .OOO+00 .OOOZ+00 .0003+00 .OOO+00 .0003+00 .000+00 .0003+00 .0003+00 8R 83 6.143Z-07 .0003.00 .OOO+00 .OOO+00 .0003+00 .0003+00 .OOO+00 .0ooo+00 .0003+00 8R 84 2.789Z-17 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 .OOO+00 .0003+00 .0003+00 KR 83N 4.765E-04 .0003+00 .OOOE+00 .000E+00 .0003+00 .000+00 .0003+00 .OOO+OO .0003+00 KR 85M 7.3188-03 .OOO+00 .0003+00 .OOO+OO .0003+00 .000Z+00 .000E+00 . 000z+00 .0005+00 KR 85 4.314Z-02 .OOO+OO . 000X+00 .0005+00 .0003+00 .0003+00 .000+00 .0003+00 .0003+00 KR 87 1.248Z-06 .000z+00 .0003+00 .0003+00 .0003+00 .OOO+00 .0003+00 . 000X+00 .0003+00 KR a8 2.3943-03 .000+00 .0003+00 .0003400 .0003+00 .0003+00. .0003+00 .000+00 .ooo0+oo 1128 6.412E-22 .*000+00 .0003+00 . 000+00 .0003+00 .OOO+00 .000Z+00 .0003+00 OOO.+00 1129 4.523E-10 .0003.00 .0003+00 .OOO+00 .0005400 .0003+00 .0003+00 .0003+00 .0003+00 1130M 9.324E-53 .OOO+00 .0003+00 .000+00 .0003+00 .0003+00 .0003+00 .0003+00 .000+00 1130 9.118E-05 *.000+00 .0003+00 .0003+00 .0003+00 .000+00 .0003+00 .0003+00 .0ooo+00 1131 6.288B-03 .0003+00 .0003+00 .0003+00 .OOO+00 .0003+00 .0003+00 .0003+00 .000+00 1132 4.3943-06 .0003+00 .0003+00 .000+00 .0005+00 .0003+00 .0003+00 .0003+00 .000+00 1133 3.874E-03 .000+00 .0003+00 .000Z+00 .0003+00 .0003+00 .OOO+00 .0003+00 .0003+00 X134 5.523B-11 .0003+00 .000+00 . 000+00 .0003+00 .000Z+00 .0003+00 .0005+00 .OOO+00 1135 6.4823-04 .000+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 XZ131M 9.891Z-03 .000+00 .0008+00 .0003+00 .OOO+00 .OOO+OO .0003+00 .000+00 .0003+00 XE133M 4.776Z-02 . 000+00 .0003400 .000+00 .0003+00 .0003+00 .0003+00 .000+00 .000+00 XE133 1.6583+00 .000+00 .0003+00 .000+00 .0005+00 .0003+00 .0003+00 .000+00 .0003+00 XZ135M 2.077Z-02 .0003+00 .0003+00 .OOO+00 .0003+oo .000+00 .000+00 .0003+OO .0003+00 XE135 4.846x-Ol .000+00 .0003+00 .000+00 .0003+00 .0003+00 .000+00 .0003+00 .0003+00 X3138 3.924E-31 .000+00 .000+00 .OOOR+00 .0003+00 .0003+00 .0003+00 .000+00 .0003+00 TOTALS GROUP 1 2.2753+00 .0003+00 .OOO+00 .OOO+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 GROUP 2 1.0943-02 .000+00 .0003+00 .0003+00 .oooe+00 .OOO+.00 .0003+00 .00O+00 .Ooo0+00 GROUP 3 . 0003+00 .0003+00 .0003+00 .OOO+00 .0003+00 .oooE+6O .0003+00 .0003+00 .000+00 GRND . TOT 2.2853+00 .OOO+00 .OOO+00 .OOO+00 .0003+00 .000+00 .0003+00 .0003+00 .0003+00 THE COMPARTMENT VOLUMES (A. H AND C) IN THIS TABLE ARE2 1.982E*04 .0009+00 9.707E+02 (m3)

A A

ABased R E VA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 72 ELISA-2 [LICENSNGo a SVEQE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECI ZNO. - Rel. Version 2.2 May 23,20021 28-Oct-04 PACE 33 CASEz 2 PNPS AST - FRA - BOUNDING SRC - 24 Mt DECAY - RB VENT RELEAnSS - CR - 9000 CFK (INSTANTANEOUS RELEASE FROM SOURCE)

T - .0000Z+00 hra RELEASE RATES TO ATMOSPHERE, INTERVAL RELEASES FROM .0000+00 TO .0000Z+00 hrs, CUMULATIVE RELEABIS FROM 0.0 TO .0000E.00 hre, AND RADIOAC'tIVZ-CLOUD CONCENTRATIONS WITHOUT DECAY IN TRANSIT WITH .0001+00 hre IN-TRANSIT DECAY REL. RATE XNTRV REL CUML. REL CLOUD CONC INTRv REL CUML. REL CLOUD CONC NUCLIDZ (Ci/hr) (CL) (CL) (Ci/r3) (Ci) (Ci) (Ci/m3)

BR 82 2.5523+00 .000+00 .0003+00 1.248b-06 .0001+00 1.2483-06

.0001.00 BR 83 4.870s-02 .000Z400 .000X+00 2.381Z-08 .0OOO+00 2.381Z-08

.0001400 BR 84 2.211R-12 .000Z100 .0001.00 1.01l-18 .0003.00 1.031E-18

.O0001.00 KR 83M 3.7789+01 .000S+00 .0001.00 1.847B-05 *. OOO+00 . 000Z+00 1.847E-05 KR 85M 5.8028+02 .0003+00 .0001+00 2.8371-04 .000+00 2.8373-04

.0001400 KR 85 3.420Z+03 .0008+00 .0003+00 1.672B-03 .OOO+400 .0003+00 1.6721-03 KR 87 9.892B-02 .000Z400 .000Zt00 4.836Z-08 .0003+00 4.8361-08

.0001400 KR 88 1.898Z+02 000.+00 .000Z+00 9.278Z-05 .0001.00 9.278B-05

.0001400 1128 5.0843-17 .000Z+00 .0003+00 2.485B-23 . OOOZ+00 2.4851-23

.0003+00 1129 3.586Z-05 .0001+00 .0001+00 1.753Z-11 .0003+00 1.7531-11

.000Z.00 . OOOZ+OO 1130M 7.393Z-48 .000B+00 .0001400 3.614E-54 3.6141-54

.0003.00 . OOOZ+OO 1130 7.229B+00 .OOOR+00 .000Z400 3.5341-06 .000Z+00 .0003+00 3. 534-06 1131 4.9851+02 .0001+00 .0003+00 2.4373-04 .0003+00 2.4373-04

.0001400 1132 3.4841-01 .000Z+00 .0001.00 1.703R-07 *0001.00

.0OOO300 1.703Z-07

.0001.00 1133 3.071Z+02 .000.+00 .0003+00 1.502Z-04 .0OOO+00 1.5021-04

.0003400 1134 4.379Z-06 .000Z+00 .0001+00 2.1411-12 .0003+00 2.1413-12

.0001.00 1135 5.1391.01 .00O0100 .000.+00 2.513Z-05 .0001+00 2.5133-05

.0001.00 XE131M 7.8438+02 .0001+00 .000B+00 3.834Z-04 .000Z+00 3.8341-04

.0003.00 XZ133K 3.787E+03 .0001+00 .000Z+00 1.851Z-03 1.851Z-03

.0003.00 X%133 1.315Z+05 .0001400 .0001400 6.4283-02 6.4289-02

.0001C+00 XZ135M 1.6463+03 .0003+00 .0003400 8.049Z-04 .0003400 .000B+00 8.0493-04 XR135 3.842E+04 .0001+00 .000.+00 1.878Z-02 .0001+00 1.8783-02

.0003+00 XZ133 3.1118-26 .000+00 .0001+00 1.521B-32 .0001+00 .0OOO+00 1.521Z-32 TOTALS GROUP I 1.803Z+05 .0003+OO .0001o00 8.8178-02 1.803Z+05 .0OOO+OO .000.+00 8.817B-02 GROUP 2 8.6721.02 .000+00 .0001+00 4 .240Z-04 8.6721+02 .0001+00 .0001+00 4.2401-04 GROUP 3 .0008+00 .000R+00 .0ooo000 .0008+00 .000,+00 .000+00 .000Z+Oo GPND.TOT 1.8121+05 .000o+00 .OOOE+00 8.8593-02 1.812E+05 .000z+00 .0003400 8.859Z-02 NOTZE THE ATMOSPHERIC CONCENTRATION OF RADIOACTrVITY I8 BASED ON A DISPERSION FACTOR (X/Q) OF 1.7603-03 (foclm3)

ABased A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 73 ELISA-2 (LICEN9ING & SEVERE ACCIDONT RADIOLOGICAL EVALUATIONS - ENTZCR ENG. - Rel. Version 2.2 May 23,2002] 29-Oct-04 PAGE 34 CASE# 2 PN8 AST - TEA - BOUNDINU SRC - 24 UR DECAY - RD VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELEASE FROM SOURCE)

SU1OMAY TOTAL RADIATION zXPOSURES (AIR IMMERSION PLUS INHALATION) (CONTINUOUS OCCUPANCY)

COMPARTMWNT C Beta Air Beta Air Beta Air Gamma Air Gamma Air ¢Game Air Tot. Skin Tot. Skin Tot. Skin DOSE RATE INTVL DOS CUM. DOSE DOSE RATE IN5SL DOS CUn. DOSE DOSE RATE INTlY DOS CDM. DOSE T (hours) (rad/hr) (rad) (rad) (rad/hr) (red) (red) (rom/hr) (rem) (rem)

.00004E00 .000E+00 .OOOZ+00 .000e+00 .000B+00 .0001.00 .000Z00 .000E+00 .000+00 .0001+00 5.00008-01 5.1161+00 5.757Z+00 S.7571+00 4.9231-02 5.422E-02 5.422Z-02 1.420B+00 1.590E+00 1. 5901+00 1.00001400 7.681Z-01 1.131Z+00 6.888Z+00 9.3871-03 1.1531-02 6.5751-02 2.2491-01 3.175Z-01 1.9071+00

2. *0000100 1.008B-01 2.566E-01 1.1441+00 3.103Z-03 4*6301-03 7.0381-02 4*127Z-02 8.4441-02 1.9921+00 8.0000e+00 3.5711-02 2.9211-01 7.436E+00 1.1521-03 9. 605-03 7.999E-02 .1.4781-02 1.230E-01 2. 115E+00 2.4000Z+01 3.082E-03 1.052Z-01 7.5411.00 8.033E-05 3.168E-03 8.3161-02 1 085E-03 4.1328-02 2.1561+00 9.60001+01 1.043B-04 4.4011-02 7. 585E+00 9.843X-07 8.2471-04 8.3981-02 1.9261-05 1.227B-02 2.*168+00 7.20001.02 1.126E-06 4.9901-03 7.5901+00 1.590Z-08 5.753Z-05 8.404Z-02 2. 492B-07 1.0021-03 2.1691+00 Gonads Gonads Gonads Breast Breast Breast Lungs Lungs Lungs DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

. 0000Z+OO .000H+00 .0001o+00 .0001+00 .0001+00 .000E+00 .OOO+00 .000B+00 .0001+00 .000B+00 5.0000E-01 3.867Z-02 4.2741-02 4.2741-02 5.633Z-02 6.260Z-02 6.260Z-02 .2.8421-01 3.185B-01 3.185Z-01 1.00001.00 7.108B-03 8.9701-03 5.171E-02 9.770Z-03 1.2881-02 7.5481-02 4.028E-02 6.2131-02 3.8078-01 2.0000Z+00 2.153Z-03 3.350B-03 5.5061-02 2.4961-03 4.2361-03 7.972Z-02 2.7121-03 1.142z-02 3.92I1-01 8.00001+00 7.9241-04 6.624Z-03 6.169z-02 9.0821-04 7.59SE-03 8.731E-02 7.7721-04 6.620B-03 3.987Z-01 2.4000.+01 5.410E-05 2.166Z-03 6.385Z-02 6.2271-05 2.486B-03 8.980Z-02 5.247B-05 2.117B-03 4.008Z-01

9. 6000e+01 4.9241-07 5.293B-04 6.438Z-02 6.027Z-07 6.1501-04 9.0411-02 3.9441-07 4.9981-04 4.013Z-01 7.2000E+02 5.418B-09 2.3451-05 6.441E-02 7.1371-09 2.977B-05 9.044Z-02 3.1661-09 1.629Z-05 4.0131-01 R.Marrow R.Marrow R.Narrow Bone Sur Bone Sur Bone Sur Thyroid Thyroid Thyroid DOSE RATE INTVL DOS COU. DOSO DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/hr) (ram) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00001+00 .0001+00 .000+00 .0001+00 .000X+00 .000o+00 .000H+00 .0001+00 .0001+00 .0001+00 5.00001-01 4.1903-02 4*6461-02 4.6461-02 9.287E-02 1.033B-01 1.0331-01 .6.622Z+01 7.5071+01 7.507Z+01 1.00001+00 7.4381-03 9. 6341-03 5.6098-02 1.600Z-02 2.119B-02 1.245Z-01 8 *9591+00 1.4331+01 8.9391+01 2.0000Z100 2.0443-03 3.3391-03 5.9438-02 4.021Z-03 6.883Z-03 1.314E-01 1.6511-01 2.1971+00 9.159z+01 8.00001+00 7.448B-04 6.240B-03 6.5673-02 1.4721-03 1.226Z-02 1.437B-01 8.0481-04 3.8608-02 9.163Z+01 2.40001+01 4.989Z-0S 2.0241-03 6.7701-02 1.0499-04 4.0741-03 1.4781-01 5.467E-05 2.1978-03 9.1631+01 9.6000x+01 3.293Z-07 4.667E-04 6.816S-02 1.44 0-06 1.118B-03 1.489z-01 4.598B-07 5.285E-04 9.1631+01 7.20001+02 2.691E-09 1.366B-05 6.8181-02 1.2571-08 6.1225-05 1.4891-01 4.636E-09 2.099E-05 9.163E+01

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWI)

Document ID32*5052589-01 A R E VA Prepared by, John N.Hamawi Page 74 ZLZSA-2 IL!CENSrNO & SEVERE ACCIDENT RADXOLOGXCAL RVALUATIONS - XWT CH MM0. - Ro1. Version 2.2 May 23.20021 28-Oct-04 PAGE 35 CASE# 2 PUPS AST - lEA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - CR - 9000 crM (INSTANTANEOUS RELEASE FROM SOURCE) guMMARY TOTAL RADIATION EXPOSURES (AIR 1MMBRS1ON PLUS INHALATION) (CONTINUOUS OCCUPANCY)

COMPARTMENT C Remaindr Remaindr Remaindr 3ff D.E. Bff D.e. 3ff D.3. TSD Thy TID Thy TID Thy DOSE RATE 1NTVL DOS CUM. DOSE DOSE RATE INTVM DOS CUM. DOSE DOSE RATE INTVL DOS CUN. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (ram) (rem) (rem/hr) (rem) (rem)

. 0000E.00 .000e+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003.00 . 000o00 .0003+00 5.0000e-0l 5.110o-02 S.663E-02 5. 6633-02 2.06le+00 2.3353.00 2.3353+00 9.620E+01 1.0913+02 1.0913+02 1.00005e00 8.6823-03 1.1633-02 6. 263-02 2.8071-01 4.4663-01 2.7823+00 -1.3003+01 2.0813+01 1.299E+02 2.00003+00 2.056R-03 3.6353-03 7.1893-02 7.168R-03 7.043Z-02 2.852R+00 2.362B-01 3. 1853+00 1.3313+02 8.0000z+00 7.41SE-04 6.2153-03 7.8118-02 8.065s-04 7.717E-03 2.8603+OO 6.0433-12 4.6193-02 1.3323+02 2.4000E+01 5. 0S0-05 2. 0213-03 8.0133-02 5.4883-05 2.202E-03 2.862X+00 2. 9743-40 7.6673-13 1.332Z+02

9. 6000S.01 3.7463-07 4.7623-04 8.061B-02 4.7103-07 5. 3253-04 2.8633+00 .0003+00 6.6563-41 1.3323+02 7.20002+02 3.213E-09 1.5903-Os 900628-02 4.6123-09 2. 123Z-05 2.8633+00 .0003+00 .0003.00 1.3323.02 R011093B R01109WB RGl0l9WB DOSE RATE rNTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (re=)

.OOOO+00 .0003.00 .000E+00 .0001t+00 5.00003-01 4* 430-02 4.881l-02 4. 8813-02

1. *000000 8.5213-03 1.0403-02 s. 921E-02 2.00003+00 2.879e-03 4.2533-03 6.34 6-02 8.00003+00 1.0693-03 8. 9203-03 7.2383-02 2.4000Z301 7.3923-05 2.9333-03 7.5313-02

9. 6000z+01 7.6533-07 7.4243-04 7. 606-02 7.20003+02 6.6373-09 3.286z-05 7.6093-02

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32.5052589-01 A R EVA Prepared by: John N.Hamawi Page 75 HLISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - RNTECR ENO. - Rol. VersLon 2.2 May 23,20021 28-Oct-04 PAGE 36 CA8Z# 2 PNPS AST - MtA - BOUNDING SRC - 24 Mt DECAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELEASE PROH SOURCE)

OVERALL

SUMMARY

- TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR sCENARIO DURATION (7.20002.02 hrs)

CONTINUOUS OCCUPANCY RECEPTOR/ORGAN COMPARTMENT A COMPARTMENT B COMPARTMENT C OYFSITE REC8P.

(Iemifspher) (Spherical) (Hemispher)

Beta Air (rad) .000oe00 .0003+00 7.590X+0O .0003+00 Gans Air (rad) .OOOE00 .0003400 8.4043-02 .0003.00 Tot. skin (rem) .ooo0+00 .OOO+00 2.169B+00 .000X+00

[Beta Cont. ()1 E. .001 I .001 I 96.99] I .001 Gonads (rem) .0003+00 .0003+00 6.4413-02 .0003400 Breast (rem) .0003+00 .OOO+00 9.0443-02 .0003+00 Lungs (rem) .OOOE+00 .000Z+00 4.0133-Oi .000e+00 (Inhalation (%)] E .001 1 .001 1 87.AA] C .001 R.Marrow (rem) .000Y00 .Ioooe+00 6.818E-02 .000H+00 Bone Sur (rem) .0003+00 .0003+00 1.4099-01 .0003.00 Thyroid (rem) .000Z+00 .000X+00 9.1633+.0 .0003+00 Clnhalation (E)1 C .001 I .00] C 99.941 C .001 Remaindr (ren) .000Z+00 .0003+00 8.0628-02 .OOOE+00 Bff D.E. (rem) .0003+00 .OOO+00 2.8633R00 .0003+00 tInhalation (I)] C .001 I .001 t 98.151 C .001 SID Thy (rem) .000Z+00 .0003+00 1.3323+02 .OOO00 R01109WB (re=) .0003+00 .OOO+00 7.6093-02 .000§+00 The Dose Conversion Factors (DCFn) employed by ZLISA-2 are from EPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for T2D Thy and R01109WH, which are as follow.:

TID Thy n Classical thyroid inhalation dome based on the TID-14844 DCFs (iodines only)

R11109WB a Classical whole body ineernion dose based on the Reg. Guide 1.109 DCVs (nobles and halogens only)

The beta dose to air is for immersion in an Infinite cloud.

The skin dose includes contributions from gimma radiation (finLte cloud), beta radiation (semi-infinite cloud) and ground contamination. The skin beta-contributLon percentages exclude ground contamination.

Finite-cloud correction, if any, is nuclide specific.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 76 AR EVA ELISA-2 ILICENSING & SEVERE ACCIDINT RADIOLOGICAL EVALUATIONS - ENTICH ENO. - Rel. Vorsion 2.2 Kay 23,20021 28-Oct-04 PAGE 37 CASgE 2 PNPS AST - TRA - BOUNDINO SRC - 24 RR DECAY - RB VENT RELEASES - CR - 9000 CrM (INSTANTANSOUS RELEASE FROM SOURCE)

SUMM~ARY TOTAL RADIATION EXPOSURES (AIR rNMERSION PLUS SNiATION) (PARTIAL OCCUPANCY)

COZIPARTHENT C Beta Air Beta Air Beta Air Gazm Air Ga=a Air Gamma Air Tot. Skin Tot. Skin Tot. Skin DOSE RATE 1tTrvr DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOUR DOSS RATE INTVL DOS CUM. DOSE T (hourn) (rad/hr) (rad) (rod) (rad/br) (rod) (rad) (rem/hr) (rem) (rem)

. 0000Z00 .0001+00 .000+.00 .0001+00 .0001+00 .000B+00 .0001+00 .0001.00 .0001+00 .000E+00 5.0000e-01 5.1161.00 5.757N+OO 5.757E100 4.9231-02 5.422Z-02 5.4221-02 1. 420Z+00 1.590z+00 1.590E+00 1.OOOOE+00 7.681B-01 1.131Z+00 6.888E+00 9.387Z-03 1.153Z-02 6.5751-02 2.2491-01 3.175Z-01 1.9071+00 2.00001+00 1.008Z-01 2.5661-01 7.1441400 3.1038-03 4. 630e-03 7.0351-02 4.127Z-02 8.4441-02 1.9921+00 8.0000Z00 3.571B-02 2.921B-01 7.4361+00 1.152E-03 9.6058-03 7.999Z-02 1.4781-02 1. 2301-01 2.1151+00 2.4000B+01 3.082Z-03 1. 052z-01 7.541X+00 8.0331-05 3.168Z-03 8.3161-02 1. 085-03 4.1321-02 2.1s6z+00 9.60001+01 1.0431-04 4. 4012-02 7.5851+00 9.8431-07 8.247E-04 8.398Z-02 1.926Z-05 7.360Z-03 2.163E+00 7.2000E+02 1.126B-06 4*990Z-03 7.5901+00 1. 590-08 5.7531-05 8.4041-02 2.4921-07 4.o008-04 2.1641+00 Gonads Gonads Gonads Breast Breast Breast Lunge Lungs Lungs DOSE RATE lNTVL DOS CUM. DOSE DOSE RATE flTVL DOS CUtM. DOSE DOSE RATS INTVL DOS CUM. DOSE S (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00001+00 .0001+00 .000H+00 .OOO+00 .0001+00 .0001+00 .0001+00 .0001.00 .OOO+00 .0001+00 5.00001-01 3. 867z-02 4.2741-02 4.2741-02 5.633Z-02 6.2601-02 6.260Z-02 2.8421-01 3.1851-01 3.185Z-01

1. 0000E+00 7.108Z-03 8.970B-03 5.171B-02 9.770Z-03 1.2881-02 7.5481-02 4.0281-02 6.213Z-02 3.807E-01 2.0000Z+00 2. 1531-03 3.3501-03 5.5061-02 2.4961-03 4.236Z-03 7.9721-02 2.7122-03 1.1421-02 3.9211-01

8. 00001+00 7.9241-04 6.6241-03 6 1691-02 9.0821-04 7.5958-03 8.7311-02 7.772B-04 6.6201-03 3.9871-01

2. 40001+01 5. 410*-05 2.166Z-03 6.381E-02 6.227B-05 2.4861-03 8.980Z-02 5.2471-05 2.1171-03 4.008Z-Ol 9.60001+01 4. 924E-07 3.1761-04 6.417E-02 6.027B-07 3.6901-04 9.017Z-02 3.9441-07 2. 999s-04 4.011Z-01 7.2000E+02 5.4181-09 9.3801-06 6.4181-02 7.137Z-09 1. 191-05 9.018B-02 3.166Z-09 6. 517-06 4. 011Z-Ol R.Marrow R.Narrow R.Marrow Bone Sur Bone Our Bone Sur Thyroid Thyroid Thyroid DOS RATE INTVL DOS CUM. DOSE DOSE RAT! rNTVL DOS CVM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (bourn) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/br) (rem) (rem)

.00001+00 .000E+00 .0001+00 .0001+00 .0003+00 .000+00 .0001.00 . 0001+00 .000Z+00 .000o+00

5. 0000101 4.1901-02 4.646Z-02 4. 646E-02 9. 2871-02 1.033Z-01 1.0331-01 6.6221+01 7.5071+01 7.5071+01 1.00001+00 7.4381-03 9.6341-03 5.6091-02 1.600B-02 2.119Z-02 1.2451-01 8.9s9sz00 1.4331+01 8. 9391+01 2.00001+00 2.044B-03 3.339s-03 5.943X-02 4.0211-03 6.8831-03 1.3141-01 1.6511-O0 2.1971+00 9.159Z+01 8.0000Z+00 7.448R-04 6.240B-03 6.567N-02 1.4721-03 1.2261-02 1.4371-01 8.048B-04 3. 860z-02 9.1631+01

2. 4000+01 4.9891-05 2.0241-03 6.7701-02 1.0491-04 4.074E-03 1.4781-01 5.4671-OS 2.1973-03 9.1631+01 9.60001+01 3.2938-07 2.8003-04 6.7991-02 1. 440-06 6.7111-04 1. 4841-01 4.5981-07 3.171B-04 9.1631+01 7.20001+02 2.691E-09 5.4621-06 6.798E-02 1.257z-08 2.4901-05 1.4ss8-01 .4.636z-09 8.396z-06 9.163E+02

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 77 AR EVA ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH RNa. - Rel. VorvLou 2.2 Hay 23,20021 28-Oct-04 PAGE 38 CA8B 2 PNPS AST - PRA - BOUNDING SRC - 24 HR DECAY - RH VENT RELBABES - CR - 9000 cPn (INSTANTANEOUS RELZME FROM SOURCE)

SUbMARY TOTAL RADIATION EXPOSURES (AIR nl9MRSION PLUS nMALATION) (PARTIAL OCCUPANCY)

COMPARTMENT C Remalndr Rmaindr Renaindr Bff D.E. Zff D.E. 1ff D.C. TID Thy TID Thy TID Thy DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVr DOS CUM. DOSE DOSE RATE INrVL DOS CUM. DOSE T.(hours) (rem/hr) (rem) (rem) (rem/br) (rem) (re ) (rem/hr) (rem) (ren)

.0000Z+00 .000o+00 .000R+00 .0001+00 .0oooe00 .000B+00 .0001+00 .000K+00 .0001+00 .0008+00 5.00001-02 5.210Z-02 5.663l-02 5.6631-02 2.061e+00 2.33s5+00 2.3351+00 9.620E+01 1.0911+02 1.0911+02 1.0oooo00 00 8.6821-03 1.163Z-02 6.8261-02 2.807E-01 4.4661-01 2.7821+00 1.3001+01 2.081R+01 1.2991+02 2.00001+00 2.056E-03 3.635e-03 7.189Z-02 7.1681-03 7.0431-02 2.8521+00 2.362E-01 3.1851+00 1.3311+02 8.00001+00 7.4128-04 6.21SB-03 7. 811-02 8.06s5-04 7.7171-03 2.8601+00 6.0431-12 4*.619B-02 1.3328+02 2.4000B+01 5.0051-05 2.021B:03 8. 0131-02 5.4881-05 2.202Z-03 2.8621+00 2.9741-40 7.667B-13 1.3321+02 9.6000H401 3.746E-07 2.8571-04 8.0421-02 4.7101-07 3.19SE-04 2.8631+00 .0001+00 3.9941-41 1.332Z+02 7.2000B+02 3.213B-09 6.359s-06 8.042U-02 4.6121-09 8.4931-06 2 8631+00 .000R+00 .0001+00 1.332E+02 RO11O9WB R51109wB RG1109WB DOSE RATE SNTVL DOS CUM. DOSs T (hourn) (rem/hr) (rem) (rem)

.0000E+00 .000R+00 .OOO+00 .oooe+00

5. 0000-01 4.4305-02 4.8811-02 4.8811-02 1.ooooe+00 8.5211-03 1.0401-02 5.9211-02 2.ooooe+00 2.8793-03 4.2531-03 6.3461-02 9.00001.00 1.0691-03 8.9201-03 7.238E-02 2.40001+01 7.392z-05 2.933E-03 7.531B-02

9. 60001+01 7. 63E-07 4.454R-04 7.5766-02 7.2000E+02 6.637e-09 1.3141-05 7.577E-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32*5052589-01 A R E VA Prepared by, John N.Hamawl Page 78 ELTSA-2 (LICENSING a SEVERE AcCCDrNT RADIOLOGICAL EVALUATIONS - ENTECIn MMO. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAGE 39 CASE# 2 PNPS AST - YrA - BOUNDNG S9RC - 24 RR DECAY - RB VENT RELEASES - CR - 9000 CFM (INSTANTANEOUS RELZASR FROM SOURCE)

OVERALL

SUMMARY

- TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR SCENARIO DURATION (7.20009+02 hrs)

PARTIAL OCCUPANCY RECBPTOR/ORGAN COMPARTMENT A COMPARTMENT a COMPARTMENT C OFFSITB RECEP.

(femispher) (Spherical) (emiuspher)

Beta Air (red) .000.+00 .0003+00 7.590E*00 .0003+00 Gamoa Air (rad) .000.+00 .0003+00 8.404E-02 .0003+00 Tot. Skin (rem) .0003.00 .OOO+00 2.164Z+00 .0003+00 (Beta Cont. (')] I .001 E .001 C 96.99] C .001 Gonads (rem) .000E+00 .0003+00 6.4183-02 .0003400 Breast (rem) .0003+00 .000X+00 9.0189-02 .0003+00 Lungs (ren) .0003400 .000Z+00 4.011O-01 .0003+00 (Inhalation l)t I .001 I .001 1 87.891 1 .001 R.Marrow (rem) .000N+00 .0003+00 6.7983-02 .0003+00 Bone Sur (rem) .000Z+00 .000E+00 1.48S3-01 .0003+00 Thyroid (rem) .000.E00 .0003.00 9.163E+01 .000E+00 (Inhalation (%)I t .001 1 .001 1 99.941 1 .001 Remaindr (rem) .000,+00 .0003.00 8.0423-02 .0003+00 Eff D.E. (rem) .0003+00 .000Z300 2.8633+00 .000E400 tInhalation (%)1 I .001 t .001 1 98.161 t .00)

TID Thy (rem) .000Z+00 .0003+00 1.3323+02 .0003+00 RO1109WB (rem) .000N+00 .000H+00 7.577B-02 .0003+00 The Dose Conversion Factors (DCFB) employed by ELISA-2 are from EPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for TID Thy and RGllO9wn. which are as follows TID Thy a Classical thyroid inhalation dose based on the TXD-14844 DCs (iodines only)

RG1109WB a Classical whole body insersion dose based on the Reg. Guide 1.109 DCFs (nobles and halogens only)

The beta dose to air is for iamersion in an infinite cloud.

The skin done includes contributions from 9g-a radiation (finite cloud), beta radiation (semi-infinite cloud) and ground contamination. The skin beta-contribution percentages eiclude ground contamination.

FinLte-cloud correction, itf any, is nuclide specific.

Partial occupancy has been applied only to human exposures In Compartment C.

M MNDOF THIS CASE *

- ^******* END OF ANALYSrs *******

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589O1 Page 79 AR EVA ELISA-2 Run Case #B - Main Output File

A AR EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MW!)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 80 a

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EXTECR ENGI.NPRINO. INC., WESTBOROUGH, MA RELEASE VERSION/LmVL.EL- Verlsion 2.2 RELEASE DATE .......... I May 23,2002 PROBLEM SUBMITTED ON ..t 28-Oct-04 17:45%43 SNYoS FILE ............ I *liga2-FHA-AS .e11 DATA LIBRARY FLE ......s /SCL/oe11a2-2.2/eliaa2-2.1lb OUTPUT TILE ........... s eliga2-PEA-A. .12 PBOTON SPECTRA FILE 81 t oeita2-FIZA-XA".e13 PBOTON SPECTRA FILE *2 : e1Lsa2-FIIA-zAB .o14

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Atternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hramawi Document ID32*5052589-01 Page 81 AREVA ELISA-2 (LICENSING & sgiBRE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH ZNO. - Rol. Version 2.2 Nay 23,2002) 28-Oct-04 PAGE 1 nNPU' DATA LISTING Line 1 2 3 4 5 6 7 I 9 10 11 12 Seq. 12345678901234567890123456789012345678901234S6789Ol234567890123456789012345678901234567890123456789012345678901234567890 I PNPS AST - FKA - BOUND=NG 8RC - 24 HR DECAY - RR VYEI RELEASES - EAB 2 10002 3 6 8 1 0 YrYYYy 3 10003 0 1.0 24.0 0.0 0.0 4 10004 3 0 0 5 1 1.000Z+00 .0OOE+00 .0002.00 KR XE 6 2 2.850B-03 2.150Z-03 .0003+00 BR I 7 3 0.000z+00 .000H+00 .OOO+00 zz 8 10006 -1.0001+00 .0002400 9 BR82 2.042z+02 BR82M 7'.8922+01 BR83 2.5671.03 BR84 4.7332+03 10 BR84M 1.3292+02 DR85 S .815R+03 BR86 4.3561+03 BR87 9.9212.03 11 BR88 1.1302+04 12 X128 5.7021.02 1129 1..793Z-03 1130 1.3831+03 1130K 5.402z202 13 1131 2.7171+04 1132 2 *.4112.04 1133 3.4172.04 1134 3.8152.04 14 X134K 4*0742.03 1135 3..1822+04 1136 1.5442+04 1136M 9.4462+03 15 1283K 2.567S+03 KR85 8..5511.02 XR85M 5.8801.03 KR87 1.1752+04.

16 1288 1.6621.04 KR89 2 .0962+04 XR90 2.0812.04 17 XE131M 1.905E+02 X2133 3 .417E.04 XE133M 1.0521+03 X8135 1.744E+04.

18 XB135M 6.825C.03 XZ137 3 .0072+04 Xz138 3.0371.04 XZ139 2.447+.04 19 10007 2 7.02+05 96.0 10.0 0.0 0.0 0.0 Refueling Level' 20 10010 4 21 0.0 0.5 1.0 2.0 22 10018 1 23 0.0 7.4791-04 24 10019 1 25 0.0 3.199Z-04 26 10021 1 27 0.0 3.52-04 28 99999

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 82 AREVA ELISt-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECI MO. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 2 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345670901234567890123456789012345678901234567890123456789012345678901234567890123456789012345678901234567890 1 ELISA-2 DATA LIBRARY - BASED ON ORSGZN-2 AND FEDERAL GUIDANCE REPORTS 11 AND 12 V2L1 2 RELEASE DATEt 6/28/2004 V2L2 1 3 REMARKS (START) V2L1 3 4 Source inventories are in Ci for the power level specified for each plant. V2LI 4 S Decay constants are in inverse hours. V2Ll 5 6 The entry line following the decay chains includes the decay constants V2L1 6 7 for each of three members [parent (P), daugher (D) and granddaughter V2Ll 7 8 (M)I, and the branching fractions (P-D), (D-G) and (P-). V2LI 8 9 Air Imersion DCrs are in (((Bv or Gy))/s)/(Bq/m3)], for semi-infinite cloud V2Ll 9 10 around-shine DCFs are in [((Sy or Oy))/s)/(Bq/m2)3 (surface contamination). V2Ll 10 11 Inhalation DCrs are In (gv/Bq)]. V2Ll 11 12 The inhalation DCF's are for the Lung Cleirance Class which yields the V2L1 12 13 highest Effective Dose Equivalent (1ff D.Z.)s the class is identified. V2L1 13 14 Negative DC? entries imply data not available'. V2Ll 14 15 ORGAN STID Thy Thyroid inhalation based on TID-14844 - Iodine. only. V2L1 is 16 ORGAN RG1109WB' W hole body gama dose using the Reg. Guide 1.109 DCFs. V2L1 16 17 Skin DCFs are included along with the organ DCF9, but skin is not V2L1 17 18 considered as an organ. V2L1 18 19 6/28/2004 V2L2 2 20 Added beta NeV/dis for BROS, KR89, XR90, RM90M, R890, 1136, Xel37 & C9-139 V2L2 3 21 (Based on Kocher, DOB/TIC-11026, Radioactive Decay Data Tables (1981) V2L2 4 22 READ FORMATS FOR THE RADIONUCLIDE DATA BASE V2L1 19 23 Line 1 Nuclide name and source inventories (4x,a6,10x,4e12.3) V2L1 20 24 (Note: Nuclide sequence No. is not used) V2L1 21 25 Line 2 header (a80) V2L1 22 26 Line 3 Decay chain (3 members) (9x,3(a6,6x)) V2Ll 23 27 Line 4 Decay constants & branching fractions (Ox,6e12.3) V2Ll 24 28 Line 5 Header (aBO) V2L1 25 29 Lines 6-9 18 ORIGEN-2 photons and I ICRP-38 beta (8x,6e12.3) V2L1 26 30 Line 10 Header (a80) V2Ll 27 31 Lines 11-16 Doae conversion factors (8x,6el2.3) V2LI 28 32 END REMARKS V2Ll 29 33 GENZRAL DATA BASE V2LI 30 34 10 [ORGAN NAMES - READ FORMAT (11x,6(a8,4x))j V2L1 31 35 Gonads Breast Lungs R.Mharrow Bone Our Thyroid V2Ll 32 36 Remaindr 1ff D.E. TID Thy R011091B (Skin) V2L1 33 37 4 (Pow r plants and power levels (MWt)- READ FORMAT (llx,&20,1x,e12.3) V2Ll 3' 38 PWR (33 GWD/MT 3.2%) 1.000+00 V21 35 39 PWR (50 (WDMIT 4.2%) 1.000+00 V2L1 36 40 BWR (27.5 GWD/MT 3%) 1.0001+00 V2L1 37 41 BWR (40 GWD/M? 3.4%) 1.000R+00 V2L1 3, 42 18 (ORIGEN-2 upper limit energy in each gamma group (MeV) (8x,6e12.3)3 V2L1 39 43 2.000Z-02 3.0008-02 4.5001-02 7.0008-02 1.00OZ-01 1.5008-01 V2L1 40 44 3.0001-01 4.5001-01 7.00O -01 1.000R+00 1.500Z+00 2.000X+00 V2L 41 45 2.500E+00 3.0008+00 4.0001+00 6.0001+00 8.0001+00 1.1001+01 V2L1 42

AA A R EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32*5052589-01 Page 83 46 3 Factors to convert data library DCFr to proper units, as shown V2LI 43 47 1.0 Convert air riaeron DCF to [j((v or Oy)/l)/(Dq/n3)I V2L1 4'

8 1.0 Convert ground shine DCX to [((Bv or ay)/I)/(Bq/m2)I V2L1 45 ELIA-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - EZNT3CH ZN0. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGB 3 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 123456789012345678901234567890123456789012345678901234567890123456789012345678901234567890123456789012345678901234567890

'9 1.0 Convert inhalation DCF to (SyIBql V2L1 46 50 18 Air gaa DCF for sei-infinite monoener. cloud arc [(Gy/s)/(Bq/m3)3 V2L1 47 51 6.676B-16 1.6693-15 2.5033-15 3.839B-15 5.674B-15 8.345B-15 V2L1 *8 52 1.502B-14 2.503E-14 3.8398-14 5.674B-14 8.3453-14 1.168R-13 V2LI 49 53 1.5023-13 1.836B-13 2.3373-13 3.338Z-13 4.6733-13 6.342B-13 V2L1 50 54 18 Air gaa DCF for monoenerg. ground-surface source I(Oy/s)/(Bq/=2)) V2L1 51 55 1.829E-16 1.493B-16 9.8353-17 8.181Z-17 9.7673-17 1.4361-16 V2L1 52 56 2.760B-16 4.7851-16 7.3183-16 1.0503-15 1.4573-15 1.9101-15 V2L1 53 57 2.325E-15 2.710B-15 3.2433-15 4.1941-15 5.3863-15 6.759B-15 V2L1 54 58 18 skin gas- n DCF for semi-infinite monoener. cloud arc j(Sv/s)/(BE/q0)3 V2L1 55 59 1.138B-16 7.690Z-16 1.467Z-15 2.717R-15 4.416B-15 6.737B-15 V2L1 56 60 1.239E-14 2.0732-14 3.193R-14 4.7543-14 7.1081-14 1.012z-13 V2L1 57 61 1.317e-13 1.6241-13 2.0893-13 3.030Z-13 4.305B-13 5.922E-13 V2L1 58 62 RADIONUCLIDE DATA BAJSZ V2L1 59 63 1 H 3 (Src Ci) 1.471E+01 2.186E+01 1.7443+01 2.5361+01 V2L1 60 64 Decay chain, decay constants and branching fractions V2LI 61 65 3 V2L1 62 66 6.403203-06 .00000+00 .00000+00 .000Z100 .0003+00 .OO0+.00 V2L1 63 67 ORIGXN-2 18--group phot/dis, and ICRP-38 betas (MeV/din) V2L1 64 68 .0003400 .0001.00 .OOOE+00 .0001+00 .0003+00 .000+.00 V2L1 65 69 ,0003+00 .000E+00 .oooe+00 .0001+00 .OOOE+00 .0001+00 V2L1 66 70 .0003400 .000+00 .ooo0+00 .0003+00 .OOO300 .0001.00 V2Ll 67 71 5.600R-03 V2L1 68 72 ICRP-38 Orgi em DCrc - Air 1- r, Grnd shine, Inbal/Clasa V V2L1 69 73 .0003+00 .OOOR+00 2.7503-18 .0008+00 .OOOE300 .000!+00 V2L1 70 74 .000X+00 3.3103-19 .0001+00 .0001+00 .000Z+00 V2L1 71 75 .000H+00 .000+00 .0001+00 .0003+00 .OOOE+00 .000r.*00 V2L1 72 76 .000+00 .000+00 .oooe000 .0003+00 .000+00 V2L1 73 77 1.730B-11 1.730Z-11 1.7303-11 1.730R-11 1.730Z-11 1.730R-11 V2L1 74 78 1.730R-11 1.73O0-11 .0001+00 .0003o+00 V2L1 75 79 2 C 14 (Src Ci) 3.125E-06 4.723R-06 3.772Z-06 5.4673-06 V2L1 76 80 Decay chain, decay constants and branching fractions V2L1 77 81 C 14 V2L1 78 82 1.380161-08 .000003+00 .000003E00 .0001+00 .0001+00 .0003+00 V2L1 79 83 ORIOEr-2 18--group phot/dis, and ICRP-38 betas (MeV/dil) V2L1 80 84 .000E.00 .000X+00 .0003+00 .0003.00 .0001+00 .0003+00 V2L1 81 8S .0OOO+00 .0001+00 .OOO+00 .OOO+00 .0001+00 .0003+00 V2L1 82 86 .0003+00 .0oooe00 .000N+00 .OOO+00 .000oe00 .0001+00 V2L1 83

AA PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 84 87 4.*9403-02 V2L1 84 88 ICRP-38 Organ DCra - Air i=mer, arnd shine, IXnal/Class c V2L1 85 89 2.590Z-19 3.520R-19 l.530E-19 1.210Z-19 7.060Z-19 2.1908-19 V2L1 86 90 1.540B-19 2.240B-19 .000Z+00 .OOOE+00 2.430E-16 V2L1 87 91 2.220Z-20 2.520B-20 8.650E-21 7.250E-21 4.630Z-20 1.2503-20 V2L1 88 92 1.030Z-20 1.610B-20 .0001+00 .0OOE+00 7.460Z-20 V2L1 89

(.... etc., for a total of 414 radionuclides .... ),

ZLISA-2 (LICENSING a SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ZNTZCH MNM. - Rel. Version 2.2 Mny 23,20021 28-Oct-04 PAGE 4 CASZ# I PNPS AST - YRA - BOUNDING SRC - 24 KR DECAY - RB VENT RELEASES - EAB (INSTANTANEOUS RELEASE FROM SOURCE)

LISTING Or INPUT DATA PATHWAY OPTION u 3 (COMP. A -- > SITE)

COMPARTMENT A: Refueling Level TOTAL FREE AIR VOLUME (ci ft) 7.0001+05 FILTERED RECIRCULATION RATE (cfm) - .000.+00 LMAM RATE TO ATMOSPHERE (frae/day) - 9.6008+01 FILTER REMOVAL EFFICIENCIES AND TIME-DEPENDENT MULTIPLIZR8 FOR RECIRCULATION RATES. LEAR RATES, COMP. A FLOW BETWEEN SPRAYED AND UNSPRAYED AREAS, AND FILTER BYPASS FRACTIONS ARE GIVEN BELOW.

NO. OF DISCRETE TIME VALUES IN INPUT - 4 INTERMEDIATE RESULTS WILL BE PRINTSD AT THE FOLLOWING TIMES Mhrs)t

.0000E+00 PROBLEM END TIME (hours) = 2.00001+00 RELEASE RATES AND DOSE RATES ARE PRIOR TO TIME-STHP CHANGES, IF ANY.

ONLY. EUACT SOLUTION or THE DIFFERENTIAL EQUATIONS WAS EMPLOYED IN TSE ANALYSIS.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-505258901 Page 85 AREVA ELISA-2 (LICENSfNG & SZVHRZ ACCIDENT RADIOLOGICAL EVALUATIONS - MNTECH BNM. - Rol. Version 2.2 May 23,2002] 28-Oct-04 PAGE 5 CASE# 1 PNPS AST - PHA - BOUNDING SRC - 24 RR DECAY - RD VENT RELEASES - HAD (INSTANTANEOUS R8LRASE FROM SOURCE)

RECIRCULATION, EXHAUST AND INTAME FILTZR REMOVAL EFFICISNCINS (fractionu)

COMPARTMENT A RECSRC. COMPARTMENT B RECSRC. COMPARTMENT C RECIRC. EXHAUST TO ATMOSPEZRE INTAKE TO COMPART. C NUCL. - --------------------- ---------------------- ---------------------- ---------------------- ----------------------

GROUP FORM 1 FORM 2 FORM 3 FORM 1 FORM 2 FORM 3 FORM I FORM 2 FORM 3 FORM 1 FORM 2 FORM 3 FORM 1 FORM 2 FORE 3 1 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 2 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 3 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 USER-SPECIFIED CLASSIFICATION OF RADIONUCLIDES AND INSTANTANEOUS FRACTIONAL RELEASES FROM THE SOURCE (AT T-0)

GROUP R L Z M B N T S FORM 1 FORM 2 FORM 3 I KR XE 1. OOOE00 .0001+00 .000B+00 2 BR r 2.850E-03 2.150Z-03 .000x+00 3 zZ .OOOR+00 .0001+00 .0001+00 ELEMENT ZZ* STANDS FOR THE RBMAINrNG DATA-LIBRARY ELXMZNTS/NUCLXDES NOT LISTED ABOVE, IF ANY.

A PNPS- Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by, John N.Hamawi Document ID32-5052589-01 Page 86 ARE VA ELISA-2 ILICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH NM. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 6 CASt 1 PNPS AST - FRA - BOUNDING SRC - 24 KR DECAY - RD VENT RELEASES - BAB (INSTANTANEOUS RELEASE FROM SOURCE)

TIME INTERVAL CONCEN"R. GAMMA DEPOSITION BREATHING EXR.FILT. COMPART. C COMPART. C X/Q %/Q D/Q RATE BYPASS rNT.FILTER OCCUPANCY (bourn) (sec/m3) (se /w=3) (1/m2) (.3/sec) FRACTION BYPASS FR. FACTOR

.0000E+00 - 5.0000E-01 7.4793-04 3.1993-04 .0003+00 3.500R-04 .000R+00 .0003+00 1.oooe+00 5.0000e 1.0000E+00 7.479X-04 3.199Z-04 .000e+00 3. 500Z-04 .000E+00 .000Z+00 1.000E+00 1.0000e+00 - 2.0000E+00 7.4793-04 3.199E-04 .000e+00 3.500Z-04 .0003+00 .OOO+.00 1. 000E+00 TIME INTERVAL COMPART A MULTIPLIERS COMPART B MULTIPLIERS COMPART C MULTIPLIERS FLOW KULT.

(IF APPLICABLE) (IF APPLICABLE) (IF APPLICABLE) SPRAYBD ARBA (hours) LEM RATE REC.YILTER LEAK RATE REC.FILTER INTAKE/EXE REC.FILTXR TO UNSPRAYED

.0000E+00 - 5.0000E-01 1.000Z+00 1.000B+00 1.000Z+00 1.000Z+00 1.0003+00 1.0003+00 1. 0003+00 5.0000Z 1.0000X+00 1.0003+00 1.000+00 1.0003Z00 1.0003+00 1.0003+00 1.000+00 1. 0003+00 1.0000R+00 - 2.00003+00 1.000+00 1.000+00 1.0003E00 1.0003+00 1.0003+00 1.0003E00 1.000Z+00 ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH ENG. - Rol. Version 2.2 May 23,2002] 28-Oct-04 PAGE 7 CASE# 1 PNPS AST - FPA - BOUNDING SRC - 24 BR DECAY - RR VENT RELEASES - EAR (INSTANTANEOUS RELEASE FROM SOURCE)

USER-SPECIFIED SOURCE INVENTORY NUCLIDE GROUP (c NUCLIDS CROUP (CL) NUCLIDE GROUP (CI)

BR 82K 2 7.89203+01 KR 87 1 1.17503.04 1134 2 3.8150+04 BR 82 2 2.0420E+02 XR 88 1 1.66203+04 r135 2 3.18203+04 BR 83 2 2.5670z+03 RR 89 1 2.0960Z+04 1136K 2 9.44603+03 BR 84m 2 1.3290s+02 FR 90 1 2.08103+04 1136 2 1.54403+04 BR 84 2 4.73303+03 1128 2 5.7020r+02 X3131-K 1 1.90503+02 BR 85 2 5 *81503+03 1129 2 1.79303-03 X3133M 1 1.05203+03 BR 86 2 4.3560R+03 1130M 2 5.40203+02 X3133 1 3.41703+04 BR 87 2 9.92103+03 1130 2 1.38303+03 X31353 1 6.82503+03 BR 88 2 1.13003+04 1131 2 2.71703+04 X3135 1 1.7440E+04 KR 83M 1 2.5670E+03 1132 2 2.4110E+04 X3137 1 3.0070B+04 KR 85K 1 5.8900oo03 1133 2 3.41703.04 X3138 1 3.03703+04 KR 85 1 8. 5510z+02 X134M 2 4.07403+03 X1139 1 2.44703+04

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID 32-5052589-01 Page 87 AR EVA ZLISA-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH KNO. - Rol. Vorsion 2.2 May 23,20021 28-Oct-04 PAGE 8 CASE# 1 PNPS AST - FlA - BOUNDING SRC - 24 RR DECAY - RD VENS RBLBASES - XAB (INSTANTANEOUS RELEASE FROM SOURCE)

SOURCE INVENTORY FOLLOWING 2.4003+01 HOURS OF RADIOACTIVE GROWTH AND DECAY PRIOR TO RELEASE NUCLIDE GROUP (Ci) NUCLIDE GROUP MC) NUCLIDE GROUP (Ci)

BR 82 2 1.2761R+02 8R 89 3 9.0150Z-01 XE133M' 1 9.46699+02 BR 83 2 2.4352r+00 1128 2 2.54193-15 X8133 1 3.28693+04 BR 84 2 1.10578-10 1129 2 1.7930B-03 X1l35M 1 4.1160E+02 BR 83M 1 9.44453+00 1130M 2 3.69633-46 X1135 1 9.60503+03 KR 85M 1 1.45053.02 1130 2 3.61473+02 SZ138 1 7.77763-27 KR 85 1 8.5501Z+02 X131 2 2.49263+04 csl3S 3 6.60143-06 KR 87 1 2.47293-02 X132 2 1.74193+01 C8137 3 7.29873-03 KR 88 1 4.7443U+01 1133 2 1.53579+04 C5138 3 8.23373-10 RE 87 3 3.6297E-ll X134 2 2.18963-04 C8139 3 1.41353-43 RB 88 3 5.29253.01 X135 2 2.5697E.03 B137M 3 6.9045B-03 RB 89 3 1.6731E-25 X3131M 1 1.96063+02 B1139 3 1.27008-03

-A

A ARE VA PNPS. Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 88 BLITA-2 (LICENSING a SIVERE ACCID1?NT RADIOLOGICAL EVALUATIONS - ENTECH ENa. - Bel. Veralon 2.2 May 23,20021 28-Oct-04 PA.E 9 CASE# 1 PUPS AST - YEA - BOUNDING SRC - 24 1R DECAY - RB VENT RELEASES - ZAB (INSTANTANROUS RZLEASE FROM SOURCE)

T - .0000Z+00 hrn DISTRIBUTION OF RADIOACTIVITY NUCLIDE COMPARTS. CHEM-SPRAY RZC.FILTSR COMPARTS. RZC.FXLTIR EMR.FILTER OFFSITE A IN COMP. A IN COMP. A B IN COMP. D TO ATMOSP. GROUND DZP (Ci/m3) (CO) (CI) (Ci/=3) (Ci) (CI) (Ci/m2)

BR 82 3.219B-05 .000Z+00 .0001+00 .0001+00 .0001+00 .0001+00 .OOO+00 BR 83 6.143B-07 . 000Z+00 .000E+00 .000Z+00 .0001+00 .000X+00 .0001+00 BR 84 2.789Z-17 .OOOZ1400 .OOO+00 .0001+00 .0001+00' .0003+00 .000X+00 KR 83W 4.765B-04 .000B+00 .000Z+00 .0001+00 .0001+00 .0001.00 .0001+00 RR 85M 7.318B-03 . 0001+00 .000z+00 .OOO+00 .0001+00 .0001+00 .OOO+00 XR 85 4.314Z-02 .000o+00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 XR 87 1.248B-06 .0001.00 .0001+00 .0001+00 .0001+00 .000+00 .000B+00 XR 88 2.3943-03 . 0001+00 .0001+00 .0001+00 .0001+00 .0001.00 .OOO+00 X128 6.412B-22 .0001+00 .0001+00 .0001+00 .0001+00 .000Z+00 .000Z+00 X129 *.5238-10 .0001.00 .0001+00 .0001+00 .0001+00 .OOO+00 .0005+00 1130M 9.324B-53 .000X+00 .0001+00 .0001+00 .0001+00 .000Z+00 .0001+00 1130 9.118Z-05 .000H+00 .OOO+00 .000H+00 .0001+00 .000E+00 .0001+00 1131 6.288Z-03 .000Z+00 .0001+00 .0001+00 .000B+00 .0001+00 .0001+00 1132 4.394E-06 .0001+00 .0001+00 .000Z+00 .0001+00 .OOO+00 .0005+00 1133 3.8741-03 .000+E00 .0003+00 .0001+00 .0001+00 .OOO+00 .OOO+00 1134 5.523Z-11 .OOO+00 .OOO+00 .OOO+00 .0001+00 .000Z+00 .000E+00 1135 6.4821-04 .0001E00 .OOO+00 . 000+00 .000oo00 .0001+00 .0001+00 XR131H 9.8911-03 .O00E+00 .OOO+00 .0001+00 .ooo0+00 .0001+00 .0001+00 X2133M 4.776E-02 .000Z+00 .OOOZ+00 .0001+00 .0001+00 .0001+00 .0001+00 XR133 1.6581.00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 2.077E-02 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 .000R+00 XE135 4.846Z-01 .0001+00 .0001.00 .0001+00 .0001+00 .0001+00 .OOO+00 XE138 3.9241-31 . 000+00 .000R+00 .0001+00 .000K+00 .0001+00 .0001.00 TOTALS GROUP 1 2.275E+00 .0001.00 .0001+00 .000Z+00 .000X+00 .0001+00 .0001+00 GROUP 2 1.094Z-02 .0001+00 .000X+00 .0001+00 .0001+00 .0001+00 .OOO+00 GROUP 3 .0001+00 .0001+00 .OOO+00 .0001+00 .- 000+C0 .0001+00 .0001+00 GRND.TOT 2.2851+00 .0001+00 .0001+00 .OOO+00 .0001+00 .0001+00 .000Z+00 THE COMPARTMENT VOLUMES (A AND B) IN THIS TABLE ARE1 1.982Z+04 .000B+00 (Mfi3 I

A A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-505258901 A R E VA Prepared by: John N.Hamawi Page 89 ELISA-2 (LICENSING A SEVERE ACCIDENT RADIOLOGICAL EVALUATION8 - ENTICH bNM. - Rol. Version 2.2 May 23,20021 28-oct-04 PAGE 10 CASE# 1 PNPS AST - FHA - BOUNDING SRC - 24 HR DECAY - RD VENT RELEASES - RAB (INSTANTANIOUS RELEASE FROM SOURCE)

T n .00001+00 bra RELEASE RATES TO ATMOSPHERE, INTERVAL RELEASES FROM .oooo000 TO .OOOOE+00 bra, CUMULATIVE RZLEAZSS rROM 0.0 TO .OOOOE+00 bra, AND RADIOACTIVE-CLOUD CONCENTRATIONS WITHOUT DECAY IN TRANSIT WITH .0001+00 bra IN-TRANSIT DECAY REL. RATE INTRV REL CUML. REL CLOUD CONC REL. RATE INTRV REL CUML. REL CLOUD CONC NUCLIDE (CL/hr) (C1) (CIM (CI/m3) (Cl/br) (CL) (Cl) (Ci/-3)

BR 82 2.S52E+00 .0001.00 .000.+00 5.302Z-07 2.552z+00 .0001+00 .0001+00 5.302Z-07 BR 83 4.870B-02 .000+00 .000+00 1.012b-08 4.870E-02 .0001+00 .0001+00 1.012Z-08 BR 84 2.211Z-12 .0002+00 .OOOZ+OO 4.594E-19 2.211Z-12 .0001+00 .0001+00 4.5941-19 KR 83M 3.778E+01 .OOO+00 .000+00 7.848Z-06 3.7781+01 .0001+00 .0001+00 7.848E-06 KR 85M 5.8021+02 .00Z+00 .0001+00 1.2051-04 5.8023+02 .0001+00 .0002+00 1.2051-04 KR 85 3.420E+03 .0001.00 .000Z+00 7.105E-04 3.4201+03 .000x+00 .0002.00 7.1053-04 KR 87 9.892E-02 .0001+00 .0001+00 2.0551-08 9.892B-02 .0001.00 .OOO+00 2.055Z-08 KR 88 1.898E+02 .OOO+00 .0001+00 3.943e-05 1.898Z+02 .000X+00 .0001.00 3.9438-05 1128 5.084Z-17 .000+.00 .000100 1.056E-23 5.0841-17 .0001+00 .0002.00 1.056Z-23 1129 3.586E-05 .OOO+00 .OOO+00 7.450B-12 3.5861-05 .0001+00 .0001.00 7.450e-12 1130K 7.393Z-48 .OOO+00 .0001+00 1.5361-54 7.3932-48 . OOO+00 .0001+00 1.5361-54 1130 7.229z+00 .OOO00 .0001+00 1.502B-06 7.2291+00 .0001+00 .OOOZ+00 1.502e-06 1131 4.9852+02 .0001+00 .000Z+00 1.036E-04 4.985E+02 .OOO+00 .OOO+00 1.036e-04 1132 3.4842-01 .000Z+00 .0001.00 7.2381-08 3.4841-01 .OOO+00 .000o+00 7.2381-08 1133 3.0711+02 .000+00 .000+00 6.381Z-05 3.071Z+02 .0001+00 .000o+00 6.381Z-05 1134 4.379Z-06 .OOO+00 .0001+00 9.098Z-13 4.379Z-06 .0002.00 .0001+00 9.098Z-13 1135 5.139E+01 .OOO+00 .000Z+00 1.0681-05 5.1391+01 .0001+00 .0001+00 1.068Z-05 XE131M 7.843E+02 .OOO1+00 .0001+00 1.6291-04 7.843E+02 . 000x+00 .0001+00 1.6293-04

XB133M 3.7871+03 .OOO+00 .0001o00 7.8671-04 3.7871+03 .0002+00 .0003+00 7.8671-04 XZ133 1.3151+05 .000Z+00 .0001+00 2.731Z-02 1.3151+05 .OOO+00 .0001+00 2.731Z-02 XZ135M 1.646E+03 .0001+00 .0001+00 3.420Z-04 1.646Z+03 .0001+00 .0001.00 3.420Z-04 XZ135 3.8421+04 .0001+00 .0001+00 7.9828-03 3.842E+04 .0001+00 .0001+00 7.982Z-03 XS138 3.111Z-26 .000+00 .0003+00 6.463Z-33 3.111Z-26 .0003+00 .0001+00 6.463E-33 TOTALS GROUP I 1.803E+05 .OOOZ+00 .OOOZ+00 3.7471-02 1.8031+05 .OOO+00 .0003.00 3.747B-02 GROUP 2 8. 6721+02 .000+00 .OOOE+00 1.8021-04 8.6721+02 .OOO.00 .0001.00 1.802Z-04 GROUP 3 .0001+00 .000+00 .000E+00 .0001+00 .000+00 .0001+00 .0001+00 .OOO+00 GRND.TOT 1.812Z+05 .OOOE+00 .000+00 3.765Z-02 1.812Z+05 .0001+00 .0002+00 3.765Z-02 NOTEs THE ATMOSPHERIC CONCENTRATION Or RADIOACTIVITY IS BASED ON A DISPERSION FACTOR (X/Q) OF 7.4793-04 (selmi3)

I I

I i

A

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 90 AR E VA ELI8A-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL IVALUATIONS - ENTECH ENO. - Rel. Version 2.2 may 23,20021 2l-Oct-04 PAGE 11 CASE# 1 PNPS AST - VIA - BOUNDfINO SEC - 24 HR DECAY - RB VENT RELEASES - lAB (rNOTAMlANIOt7 RELEASE FROM SOURCE)

T = .00001+00 bra zXTzRNAL RADIATION RxPOSURE DUE TO AIRBORNE RADIOACTIVITY (CoNTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSZ8 ARE FROM .0000E+00 TO .0000E+00 br.)

Beta Air Beta Air Gamna Air Gamat Air Tot. Skin Tot. Skin Thyroid Thyroid Bff D.E. 1ff D.E.

DOSE RATE INMW DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOWS RITE IITVL DOS DOSE RATE INTVL, DoS NUCLIDE (rad/hr) (rad) (rad/hr) (rad) (rew/hr) (rea) (rem/br) (rem) (r/b/hr) (re=)

BR 82 1.311Z-04 .000X+00 5.325-04 .000OZ00 4.887z-04 .OOO+00 3.927Z-04 .000.+00 3.9271-04 .0001+00 BR 83 5.782Z-06 .0001+00 2.878z-08 .000+.00 2.4611-06 .0003400 2.191Z-08 .0001.00 2.202Z-08 .0001.00 BR 84 1.004E-15 .OOO+00 3.123Z-16 .0001+00 7.877Z-16 .000E+00 2.487E-16 .0001+00 2.463B-16 .000X+00 KR 83M 5.402E-04 .0oooe00 7.691B-06 .0001+00 1. 941-06 .000E+00 2.875Z-08 .OOO+00 6.707B-08 .OOO+00 XR 85M S.473R-02 . oooe+00 7.2491-03 .0001+00 2.7991-02 .000E.00 5.034Z-03 .0001+00 5. 137B-03 .0001+00 XR 85 3.165R-01 .000oo00 5.968Z-04 .0001.00 1.2431-01 .0001.00 4.777Z-04 .000+00 4.8173-04 .0001+00 KR 87 4.8391-05 .0ooo+00 6.196Z-06 .000+.00 3.035-OS .0003.00 4.8351-06 .0001+00 4. 824-06 .0001+00 KR 88 2.554-02 .000oo00 2.931Z-02 .0001+00 3.6821-02 .0003+00 2.314B-02 .0001+00 2. 291Z-02 .0001+00 R3 87 .000z+00 . 000+00 .0001.00 .0003+00 .0003.00 .000H400 .0003.00 . 000Z+00 .000E+00 .0003+00 RB 88 .0001+00 .0001.00 .0001+00 .0001+00 .0001+00 .0001+00 .000X+00 .000E+00 .0001+00 .OOO00 1128 1.4053-20 .000oo00 3.423R-22 .OOO+00 7. 1921-21 .0001.00 2.4851-22 .0001+00 2.5033-22 .0003+00 1129 8.453Z-10 .OOO100 6.9911-11 .0001+00 6.292Z-11 .0001+00 1 638Z-1 .000Z+00 1. 613Z-11 .0001+00

. OOOS+OO 1130M .0003.00 .OOOR+00 6.937B-53 .0001.00 5.6321-53 .0001.00 .000.+00 .0001+00 .0003+00 .000H+00 1130 7.938z-04 .000E+00 1. 223Z-03 .OOO+00 1.355-03 .0001.00 8.8993-04 . 000X+00 8. 899Z-04 .0001+00 1131 3.531R-02 .000Z.00 1.5021-02 .000E+00 2.4491-02 .0001.00 1. 0683-02 .00O1+00 1.074E-02 .0001+00 1132 6.375B-OS . 000+00 6.2821-05 .0001z+O 8.188Z-05 .0001.00 4. 6181-05 .OOO+00 4.6183-05 .0001+00 1133 4.659e-02 .0003+00 1.473R-02 .000+.00 3.3113-02 .0001+00 1. 065Z-02 .0003+00 1.0693-02 .0003+00 1134 1.007Z-09 . OOO+00 9.089Z-10 .0001.00 1.2421-09 .0001.00 6.738Z-10 .0003Z00 6.7383-10 .000+00 1135 6.969B-03 .0001+00 6.397B-03 .0001.00 8.4721-03 .0003+00 4. 873Z-03 .OOO+00 4.8541-03 .0001.00 X1131M 4.167E-02 .0001+00 1.2451-03 .0003+00 9.568B-03 .0003.00 3. 6301-04 .0001+00 3. 6111-04 .0001+00 XZ133M 2.690B-01 .0001+00 1.2451-02 .OOOR+OO 9.765Z-02 .0001+00 6. 096B-03 .0001+00 6. 1403-03 .0001+00 XZ133 6.5921+00 .OOO100 4.7223-01 .0001+00 1.3584+00 .0003+00 2.350Z-01 .0001+00 2. 4283-01 .000O+00 X3135S 5.931B-02 .OOO+00 5.620B-02 .0001+00 7.303Z-02 3.9753-02 .000H+00 3.975Z-02 .000.+00

.0001+00 XR135 4.503E.00 .OOO00 7.5271-01 .OOO+00 2.4871+00 5.366Z-01 .0003+00 5.4123-01 .0001+00 XE138 7.731Z-30 .0001+00 2.766Z-30 .0003+00 6.0271-30 .000.+00 2.1253-30 .0003.00 2.125Z-30 .OOO+00 C8135 .000oz00 .000+.00 .0001.00 .0001.00 .0001+00 .0001.00 .0003.00 .0001+00 .000R.00 .0001+00 CS138 . 00o0100 .0001+00 .0001.00 .0003+00 .000o+00 .000E+00 .000.00 .0001+00 .0003+00 .0001.00 JI

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by John N.Hamawi Document ID32.5052589-01 Page 91 AR EVA ZLISA-2 [LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH ENO. - Rel. Version 2.2 May 23,20021 28-Oct-04 PAGE 12 CASE# 1 PNPS AST - FHA - BOUNDING SRC - 24 RR DECAY - RD VENT RELEASES - EAB (INSTANTANEOUS RELEASE FROM SOURCE)

T . OOOOR+00 hra EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE YROM .0000E+00 TO .OOOO00 hre)

Beta Air Beta Air aOc-n Air GOain Air Tot. Skin Tot. Skin Gonads Gonads Breast Breast DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS (rad/hr) (red) (rad/hr) (rad) (rem/hr) (rem) (rem/br) (rem) (rem/hr) (ren)

GROUP 1 1.1863+01 .0003+00 1.3323+00 .0003+00 4.2155+00 .000z+00 8.S613-01 .0003+00 9.939R-01 .0003+00 GROUP 2 8.9873-02 . 0001+00 3.797B-02 . 0003+00 6.799Z-02 .0001+00 2.6963-02 .0003+00 3.0793-02 .0001+00 GROUP 3 .000oe00 .000.+00 .0003.00 .000R+00 .000.+00 .0003.00 .0003+00 .0003+00 .0003+00 .OOO+500 GRND.TOT 1.195E+01 . 000M+00 1.3705+00 .0003+00 4.2835+00 .0001+00 8.83 1-01 .0003+00 1.0253+00 .0001+00 CUM. TOTAL FROM TnO .OOO+00 .0003+00 .0003+00 .0003+00 .0003+00 Lungs Lung. R.Narrow R.Marrow. Done Sur Bone Sur Thyroid Thyroid Remaindr Remaindr DOSE RATE INTVL DOS DOSS RATE INVVL DOS DOSE RATE INTVL DOS DOSE RATZ INMVL DOS DOSE RATS INTVL DOS (rem/hr) (rem) (ren/hr) (rem) (rem/hr) (rem) (rem/hr) (rem) (rem/br) (rem)

GROUP 1 7.9141-01 .0003+00 7.228B-01 .0003+00 2.0965+00 .0003.00 8.4653-01 .000Z+00 7.5333-01 . 000+00 GROUP 2 2.6841-02 .0001.00 2.596B-02 .000.E00 4.705E-02 .0003.00 2.7533-02 .OOO.00 2.562E-02 .0003+00 GROUP 3 .0001.00 .000z+00 .0001+00 .0001+00 .0001+00 .0003+00 .0001+00 .0003+00 .0005+00 .0005+00 GRND.TOT 8.1833-01 .0003+00 7.487x-01 .0003+00 2.143s0oo .000+.00 8.7403-01 .OOO+00 7.789s-01 .000E+00 CUM. TOTAL YROM TnO .ooo0+00 .0003o00 .0003+00 .000.+00 .000o+00 Eff D.E. Zff D.E. TID Thy TID? Thy RG1109WB R1O109WB DOSE RATE INTVL DOS DOSS RATE INTVL DOS DOE RATE INTVL DOS (rem/hr) (rem) (rem/hr) (rem) (rem/br) (rem)

GROUP 1 8.5873-01 .0003+00 .0005+00 .OOO3+00 1.2233+00 . 0003+00 GROUP 2 2.7613-02 .oooe+00 .0003+00 .000x+00 3.567Z-02 .0003+00 GROUP 3 .0003+00 .0003.00 .000Z+00 .0003+00 .OOOs+00 .0003+00 GRND.TOT 9.863R-01 .0003+00 . 000+00 .0003+00 1.2583+00 .000o00 CUM. TOTAL MROM T-0 .000N+00 .0003+00 .0003+00 I

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by John N.Harnawi Document ID32-50525894t Page 92 AR EVA ELIRA-2 [LICENSING & s5V7. ACCIDENT RADIOLOOICAL EVALUATIONS - ENTECI BNa. - R1o. Verniton 2.2 May 23,2002] 28-Oct-04 PAGE 13 CASE# 1 PNPS AST - PEA - BOUNDING SRC - 24 RR DECAY - RB VENT RELEASES - SAS (INSTANTANEOUS RELEASE FROM SOURCE)

T .OOOOE100 hre RADIATION EXPOSURE DUE TO INHALATION (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE ?ROM .00001+00 To .00001+00 hrs).

Thyroid Tbyroid zff D.E. Eff D.E.

DOSZ RATE INTVL DOS DOSE RATE INTVL DOS NUCLIDI (rem/hr) (rem) (reu/hr) (rem)

BR 82 5.092E-04 .000z+OO 1.0211-03 .0001+00 BR 83 5. 377E-08 .0001+00 1.1371-06 .OOOB+00 BR 84 6.6821-18 .0001+00 S.5S901-17 .OOO+00 KR 83M .0001+00 .000Z+00 .0001+00 .0001+00 KR 85H .odoz+OO .0001.00 .OOO+00 .000oo00 KR 85 .000E+00 .0001.00 .0001+00 .0001+00 KR 87 .0008+00 .0003+00 .OOO+00 .0001+00 XR 88 0001+,00 . 000+00 .0001+00 .000Z+00 PR 87 .OOO+00 .000+00 .0001+00 OOOE+00 RD 88 .000Z+00 .0o0o0oo .OOOE+00 .000+00 X128 2 .629E-21 .0001+00 6.303E-22 .OOOZ+00 X129 S.41*E-os .000z+00 1.6291-06 .0003+00 1130M . OOO+.00 . 0001+00 .000E+00 .0003+00 1130 1.393E-01 .0001+00 4.999E-03 .0001o+00 1131 1. 4101+02 .OOO+00 4.2921+00 .000+00 1132 5.871l-04 .000oo00 3 .4751-05 .00000oo I133 1. 4461+01 . 0003+00 4.700B-01 .000o+00 1134 1.2228-09 .0001+00 1. *506-10 .0001o+00 1135 4.211R-01 .OOO+OO 1.653B-02 .0001+00 XB13 m .000o+00 .000+00 .0001+00 .0001+00 XZ133M .000+00 .0001+00 .00011+00 .000+00 X1133 .OCOE+00 .0001+00 .000E+00 .000e+00 xz135M .000oz00 .000Z+00 .0001+00 .OOOE+00 XE135 .OOO0+00 .00oz+00 .0001+00 .000+00 X1139 .000Z+00 .000z.00 .000H+00 .0001+00 C513S .0003+00 .000+00 .0001+00 .000X+00 C8138 .0001+00 .OOOE+00 . 000o+00 .OOOB+OO

A A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemalive Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R EVA Prepared by: John N.Hamawi Page 93 BL1SA-2 [LICENSING & SEVERE ACCIDENT RADIOLOXrCAL EVALUATIONS - ENTECH BNO. - Rel. Version 2.2 May 23,20021 20-oct-04 PAGE 14 CASE# 1 NVS AST - PRA - BOUNDING SRC - 24 HR DECAY - RB VENT RELEASES - HAB . (INSTANTANEOUS RELEASE FROM SOURCE)

T a.OOOOE+00 hru RADIATION EXPOSURE DUE TO INHALATION (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE FROM .00003+00 TO OOOOE+00 hrD)

Gonad. Gonads Breast Breast DOSE RATE INTVL DOS DOSE RATE 1NTVL DOS (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 . 0003+00 .0003+00 .0003+00 .0003+00 GROUP 2 1.9483-02 .0003+00 4.882Z-02 .0003+00 GROUP 3 .0003+00 .0003400 .0003+00 .0003+00 GRND .TOT 1.9483-02 .0003+00 4*.882-02 .0003+00 CUM. TOTAL FROM T-0 .000E+00 .0003+00 Lunge Lungs R.Marrow R.Marrow Bone Bur Bone Bur Thyroid Thyroid Remsindr Remaindr DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INrVL DOS DOSE RATE NTvL DOS (rem/hr) (rem) (rem/hr) (ram) (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 .000Z00 .0003+00 .0003+00 .0003+00 .000Z+00 .0003+00 .000Q+00 .0003o00 .OOO+00 .OOO+00 GROUP 2 5.916B-01 .0001+00 4. 029o-02 .0003+00 3.6923-02 .0003+00 1.560E+02 .0003+00 5.738B-02 .OOO+00 GROUP 3 .000+00 .OOO00 .000+00 .0003+00 .000s+00 .0003+00 .0003+00 .0003+00 .0003+00 .0003+00 GRND.TOT 5.9168-01 .000.+00 4.029B-02 .000E+00 3.692B-02 .0003+00 1.560B+02 .0OOO+00 5.738B-02 .000B+00 CUM. TOTAL FROM T=0 .0003+00 .0003+00 .0003+00 .000E+00 .0003+00 Bff D.E. 3ff D.E. TID Thy TID Thy DOSE RATE INTVL DOS DOSE RATE SNTVL DOS (rem/hr) (rem) (rez/hr) (rem)

GROUP 1 .000E+00 .0003+00 .000R+00 .00o0+00 GROUP 2 4.785e+00 .000E+00 2.2703+02 .0003+00 GROUP 3 .000e+00 .0003+00 .000B+00 .0ooo+00 GRND.TOT 4.785E+00 .0003+00 2.270B+02 .0003+00 C8M. TOTAL FROM TuO .0003+00 .0003+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 94 AREVA ELISA-2 ILICENSINO & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECE ENO. - REl. Version 2.2 May 23,2002] 28-Oct-04 PAGE 15 CA5E# 1 PNPS AST - mEA - BoUNDINU SRC - 24 HR DECAY - RD VENT RZLEASEt - VW (INSTANTANEOUS RELEASE FROM SOURCE)

SUMMARY

TOTAL RADIATION EXPOSURES (AIR IMNBRSION PLUS INRALATION) (CONTINUOUS OCCUPANCY)

OUDOOR RECEPTOR eota Air Beta Air Beta Air Ga=& Air GaCa Air Geiina Air Tat. skin Tot. Skin Tot. Skin DOSE RATE INTVL DOS Cox. DOSE DOSE RATE INTVL DOS CUM. DoSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rad/br) (red) (rad) (rad/hr) (rad) (rad) (rvn/hr) (rem) (rem)

.00003+00 1.19E501 .0003+00 .0003.00 1.3703+00 .*000.E00 .0003+00 4.2833400 .000.R00 .000+00 5.0000E-01 1.640E+00 2.5893+00 2.5893400 1.9943-01 2.988E-01 2.9883-01 '6.023B-01 9.315B-01 9.315-01 1.0000E+00 2.568E-01 3.655Z-01 2.954Z+00 4.6333-02 4.938B-02 3.4823-01 1.117B-01 1.3993-01 1.071E+00 2.0000E+00 4.394Z-02 9.395E-02 3.048E+00 2.1463-02 2.776Z-02 3.7593-01 3.491E-02 5.346E-02 1. 125+00 Gonads Gonads Conado Breast Breast Breast Lungs Lungs Lungs DOSE RATE INTVL DOS CUM. DOSE DOSE RATE 1NTVY DOS CUM. DOSE DOSE RATE INTVL DOS CII. DOSE T (hours) (rem/br) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

- .0000R+00 - 9.0253-01 . .00O+00 .000B100 .. 1.073B+00 - .0003+00 .0003+00 1.4103+00 .0003+00 .0003+00 5.0000Z-01 2.3183-01 1.9708-01 1.9703-01 1.564E-01 2.3423-01 2.3423-01 2.0203-01 3.0793-01 3.0793-01 1.00003+00 3.124E-02 3.285B-02 2.2983-01 3.650Z-02 3.8783-02 2.7303-01 4.050B-02 4.794Z-02 3.558Z-01 2.00003+00 1.4853-02 1.9023-02 2.4883-01 1.701E-02 2.196X-02 2.9493-01 1.480-02 2.1118-02 3.769E-01 R.Marro. R.Marrow R.Marrow Bone Sur Bone Sur Bone Sur Thyroid Thyroid Thyroid DOSE RATE INT DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOWE RATE INTVL DOS CUM. DOSE T (hours) (rem/br) (rem) (rem) (rem/hr) (rem) (rem) (rem/br) (re=) (rem)

.00003+00 7.890E-01 .0003+00 .0003+00 2.180E+00 .0003.00 .000E+00 1.5693+02 .OOO+00 .000+00 5.0000Z-01 1.1618-01 1.724E-01 1.7243-ol 3.116E-01 4.7403-01 4.7403-01 2.1173+01 3.388Z+01 3.3883.01 1.00003+00 2.840E-02 2.9213-02 2.0163-01 6.650S-02 7.5228-02 5.492E-01 2.8693+00 4.5763+00 3.845R+01 2.00003+00 1.404Z-02 1.772E-02 2.193B-01 2.7293-02 3.704E-02 5.862B-01 C6.675Z-02 7.147E-01 3.917Z+01 Remaindr Remaindr RE indr Eff D.E. Zff D.E. Zff D.E.

TID Thy TID Thy TID Thy DOSE RATE INTV, DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/br) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.0000E+00 8.363Z-01 .0003+00 .0003+00 5.671E+00 .000+00 .0003+00 .2.2703+02 .000B+00 .0003+00

5. 0000Z-01 1.2253-01 1.8278-01 1.827Z-01 7.756B-01 1.2273+00 1.227Z+00

3.059Z+01 4.8993+01 4.899Z+01 1.0000Z+00 2.9193-02 3.058Z-02 2.1333-01 1.183B-01 1.719B-01 1.3993+00 44.122B+00 6. 602S+00 5.559Z+01 2.00003+00 1.396E-02 1.784Z-02 2.3113-01 1.671E-02 4.0583-02 1.4393+00 ,7.487B-02 1. 0103+00 5.660Z+01

/

A PNPS -Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Temm Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 95 ELISA-2 [LICENSING & SzVERE ACCIDENT RADIOLOGICAL VALUATxION9 - ENTICS mNm. - Rel. Version 2.2 May 23,2002] 28-Oct-04 PAGE 16 CASE# I PNPS AST - FEA - BOUNDING SRC - 24 RR DECAY - RD VINM RELAWES - FAB (INSTANTANEOUS RELEASE rROK SOURCE)

SUMMARY

TOTAL RADIATION EXPOSURES (AIR IMMERSION PLUS INHALATION) (CONTINUOUS OCCUVPANCY)

OUTDOOR RECEPTOR ROllO9WB R211O9WB RQ11O9WB DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem)

.OOOOE+00 1.2593+00 .000+00 .000OE00 5.0000Z-01 1.825Z-01 2.739B-01 2.739B-01 1.0000+00 4.269B-02 4.527Z-02 3.192E-01 2.0000Z+00 1.996Z-02 2.573B-02 3.449B-01

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R EVA Prepared by: John N.Hamawi Page 96 ELISA-2 (LICENSING sSZVERZ ACCIDENT RADIOLOOICAL EVALUATIONS - ENTICE ZNS. - Rol. Version 2.2 May 23,20021 28-Oct-04 PAGE 17 CASR 1 PNPS AST - FHA - BOUNDING SRC - 24 HR DECAY - RB VENT RBLEASES -AB D(ISTANTAEOUS RELEASE FROM SOURCE)

OVERALL SUMIARY - TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR SCENARIO DuRATION (2.00001+00 hrn)

CONTINUOUS OCCUPANCY RECZPTOR/ORGAN COPARTMENT A COMPARTMENT B COMPARTMENT C OFFSITE RICEP.

(Reznispher) (Spherical) (Spherical)

Beta Air (red) .000E+00 .0001+00 .000Z.00 3.048E+00 Camm Air (rmd) .000E+00 .OOOE+00 .OOO+00 3.759E-01 Tot. skin (rem) .0001+00 .OOO+00 .0001+00 1.125Z100 (Beta Cont. (1)1 1 .00] C .001 I .00] 1 73.63]

Gonads (rem) .0001+00 .0001400 .0001.00 2.488B-01 Breast (rem) .OOO1OO .000Z+00 .0001+00 2.9491-01 Lungs (rem) .0001+00 .OOO+.00 .000H+00 3.769R-01 (Inhalation 1)1 t .001 C .001 C .001 1 39.651 R.Marrow (rem) .OOOR+00 .000.00 .0001+00 2.1931-01 Bone Sur (rem) .0001+00 .000H+00 .0001.00 5.862B-01 Thyroid (rem) .OOO+00 .0001+00 .0001+00 3.9171+01

[inhalation I) .001 1 .001 .001 1 99.381 Remaindr (rem) .0001.00 .OOOBE00 .000oe00 2.311Z-01 Eff D.E. (rem) .0001E00 .0001.00 .0001400 1.439Z+00 (Inhalation (1% 1 .001 C .00 -1 .001 1 82.961 TID Thy (rem) .0001E00 .0001+00 .0001400 5.660E+01 RG1IO9WB (rem) .0001+00 .0005+00 .OOO+00 3.449Z-01 The Done Conversion Factors (DCFB) employed by ELISA-2 are from EPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for TID Thy and RGllO9WB, which are as followes TID Thy - Classical thyroid inhalation dosn based on the TID-14844 DCrs (iodines only)

RG1lO9WB - Classical whole body imersion dose based on the Reg. Guide 1.109 DCFs (nobles and halogens only)

The beta dose to air in for Isuersion in an infinite cloud.

The skin dose includes contributions from gama radiation (finite cloud), beta radiation (seml-infinite cloud) and ground contamination. The skin beta-contribution percentages exclude ground contamination.

Finito-cloud correction, if any, is nuclide specific.

..*--*** END OF THIS CASE ****---*

* - -- - - END Or ANALYSIS mm

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32.5052589-01 Page 97 ARE VA ELISA-2 Run Case #C - Main Output File

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 ARE VA Page 98 66668 6##I#

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8# 6 8688668 NTEC ENGINEBRINo, INC., WNSTBOROUGE, MA RELEASE VERSION/LEVEL..: Version 2.2 RELEASE DATE ........... : May 23,2002 PROBLEM SUBMITTED ON .. : 3-Nov-04 10 12:30 INPUT FILE ....-----.. : elina2 -FEA-LPZ.e11 DATA LIBRARY FILE ..... t /SCL/eliua2-2 . 2/e1isa2-2 .1b OUTPUT FILE ........... s elisa2-FHA-LPZ.o12 PROTON SPECTRA FILE 81 s e1iza2-FHA-LPZ.e13 PHOTON SPECTRA FILM 62: ellia2-FHA-LPZ.e14

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 99 AR EVA ELISA-2 (LICeNSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENSZCH ENO. - Rol. Version 2.2 May 23,20021 3-Nov-04 PAGE I INPVS DATA LISTINO Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 1234567890123456789012345678901234567890123456789012345678901234567890123456789012345678901234567890123&5678901234567890 1 PNPS AST - FRA - BOUNDING SRC - 24 RR DECAY - RD VENT RELEASES - LPZ wIazma X/Q 2 10002 3 6 8 1 0 NNYNNN N NNN YYYYYY 3 10003 0 1.0 24.0 0.0 0.0 A 10004 3 0 0 S 1 1.0001+00 .OOO+00 .000Z+00 KR XE 6 2 2.8508-03 2.1508-03 .000+.00 BR 1 7 3 0.000.+00 .0001.00 .0001+00 ZZ 8 10006 -1.0001+00 .0001+00 9 BR82 2.042E+02 BR82M 7.892Z+01 BR83 2.567R+03 BR84 4.7331+03 10 BR84M 1.328Z+02 BR85 5.815E+03 8R86 4.3561+03 BR87 9.921E+03 11 BR88 1.1301+04 12 1128 5.7021.02 1129 1.793E-03 1130 1.383E+03 1130M 5.4021+02 13 T131 2.7171+04 1132 2.411E+04 1133 3.417E.04 1134 3.8151.04 14 1134M 4.0741+03 1135 3.1821.04 1136 1.5441+04 1136K 9.446R+03 15 HR83M 2.567E+03 KR85 0.5511+02 ZR85M 5.8801+03 HR87 1.1751.04 16 KMeB 1.6621+04 KR89 2.0961+04 KR90 2.0811.04 17 XB131M 1.9051+02 XB133 3.4171.04 X1133M 1.0521+03 X8135 1.7443+04 18 XE13SM 6.8251.03 XB137 3.0071.04 XB138 3.0371.04 XB139 2.4471+04 19 10007 2 7.01.05 96.0 0.0 0.0 0.0 0.0 'Refueling Level' 20 10010 4 21 0.0 0.5 1.0 720.0 22 10018 5 23 0.0 3.692Z-05 2.0 1.9151-05 8.0 1.066Z-05 24.0 4.339Z-06 96.0 1.1941-06 24 10019 5 25 0.0 3.5511-05 2.0 1.782B-05 8.0 9.6271-06 24.0 3.7451-06 96.0 9.6561-07 26 10021 3 27 0.0 3.53-04 8.0 1.81-04 24.0 2.33-04 28 99999

A AR EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 100 ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECE ENa. - Rel. Version 2.2 May 23,2002] 3-Nov-04 PAGE 2 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 12345678901234567090123456799012345678901234567890123456789012345678901234S6713901234567890123456789012345678901234567890 ELSSA-2 DATA LIBRARY - BASED ON ORIGEN-2 AND FEDERAL GUIDANCE REPORTS 11 AND 12 V2LI 2 2 RELEASE DATEt 6/28/2004 V2L2 1 3 REMARKS (START) V2L1 3 4 Source inventories are in Ci for the vow r level specified for each plant. V2L1 4 5 Decay constants are in inverse hourn. V2LI 5 6 The entry line following the decay chains includes the decay constants V2L1 7 for each of three nembers rparent (P), daugher (D) and granddaughter V2LI 7 B (0)], and the branching fractions (P-D), (D-G) and (P-G). V2LI a 9 Air imeraion DCrs are in (((Sr or Gy))/s)/(B/n3)1, for semi-infinite cloud V2L1 9 10 Ground-ohine DCTs are in (((Sv or Oy))/s)/(Dq/m2)] (surface contamination). V2L1 10 11 Inhalation DCrs are in tSv/Bq) . V2L1 11 12 The inhalation DCF'a are for the Lung Clearance Class which yields the V2Ll 12 13 highest Effective Dose Equivalent (Eff D.3.)l the class in identified. V2L1 13 14 Negative DCF entries imply 'data not available'. V2L1 14 15 ORGAN 'TID Thy' - Thyroid inhalation based on TID-14844 - lodines only. V2L1 15 16 ORGAN 'RGl1O9WB' - Whole body gaz=& dose using the Reg. Guide 1.109 DCFa. V2L2 16 17 Skin DCrc are included along with the organ DCrn, but skin ia not V2L1 17 18 considered as an organ. V2L1 is 19 6/28/2004 V2L2 2 20 Added beta MeV/dis for BR85, KRB9, 3R90, RM90M, RB90, 1136, Xel37 & C3-139 V2L2 3 21 (Based on Kocher, DOE/TIC-11026, Radioactive Decay Data Tables (1981) V2L2 4 22 READ FORMATS FOR TUE RADIONUCLIDE DATA BASE V2L1 19 23 Line I Nuclide name and source inventories (4x,a6,10x,4e12.3) V2L1 20 24 (Note: Nuclide sequence No. is not used) V2L1 21 25 Line 2 Reader (a80) V2L1 22 26 Line 3 Decay chain (3 members) (9x,3(a6,6x)) V2L1 23 27 Line A Decay constants & branching fractions (Sx,6o12.3) V2LI 24 28 Line 5 Reader (aso) V2L1 25 29 Lines 6-9 18 ORIGEN-2 photons and 1 ICRP-38 beta (Sx,6e12.3) V2L1 26 30 Line 10 Header (aso) V2L1 27 31 Lines 11-16 Done conversion factors (8x,6.12.3) V2L1 28 32 END REMARKS V2L1 29 33 GENERAL DATA BASE V2L1 30 34 10 (ORGAN NAMES - READ FORMAT (11x,6(a8,4x))1 V2L1 31 35 Gonads Breast Lungs R.Marrow Bone Sur Thyroid V2L1 32 36 Renaindr 3ff D.E. TID Thy RG1109 WB (Skin) V2L1 33 37 4 (Power plants and power levels (NWt) - REA S FORMAT (llx,a20,1xe12.3) V2L1 34 38 PWR (33 GWD/MT 3.2S) 1.000+00 V2L1 35 39 PWR (50 GWD/MT 4.2%) 1.000E+00 V2LI 36 40 BWR (27.5 GWD/MT 3%) 1.0008+00 V2L1 37 41 BWR (40 GWD/MT 3.4%) 1.000R+00 V2L1 38 42 18 [ORIaEN-2 upper limit energy in each gamna group (MeV) (8x,6e12.3)1 V2L1 39 43 2.0008-02 3.000Z-02 4.500O-02 7.000Z -02 1.000Z-01 1.500R-01 V2LI 40 44 3.0008-01 4.50OZ-01 7.00O0-01 1.000Z +00 1.5003+00 2.000R+00 V2L1 d1 45 2.500Z+00 3.OOOE+00 4.0003+00 6.000B +00 8.000R+00 1.100E401 V2LI 42

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R E VA Prepared by: John N.Hamawi Page 101

6 3 Factors to convert data library DC?. to proper units, an shown V2L1 43

'7 1.0 Convert air Iersion DCF to [((SB or (y)/s)/(Bq/m3)I V2L1 44 a8 1.0 Convert ground shine DCY to [((8v or Oy)Iu)/(Bq/m2)J V2L1 45 ELISA-2 [LICENSING & SBVERE ACCIDENT RADIOLOGICAL EVALUATIONS - NTECH MNO. - Rea. Version 2.2 May 23,20021 3-Nov-04 PAGE 3 DATA LIBRARY PARTIAL LISTING Line 1 2 3 4 5 6 7 8 9 10 11 12 Seq. 12345678901234567890123456799012345678901234567890123456789012345678901231567890123456789012345C789012345C789012345C7890 1.0 Convert inbalation DCF to [By/Ba] V2L1 46 18 Air gama DCr for semi-infinite monoener. cloud arc j(Gy/a)/(9q/n3)j V2L1 47 6.6763-16 1.6693-15 2.503E-15 3.839E-15 5.674Z-15 8.345Z-15 V2L1 48 1.5023-14 2.503R-14 3.839e-l4 5.674Z-14 8.3453-14 1.168Z-13 V2L1 49 1.S02Z-13 1.836B-13 2.337Z-13 3.3381-13 4.673Z-13 6.342C-13 V2L1 50 18 Air gAfa DCF for monoenerg. ground-surface source [(Oy/s)/(Bq/m2)] V2L1 51 1.8291-16 1.493B-16 9.8353-17 8.181R-17 9.7673-17 1.4368-16 V2L1 52 2.7603-16 4.785Z-16 7.318B-16 1.0501-13 1.457Z-15 1.910Z-15 V2L1 53 2.3258-15 2.7103-15 3.2431-15 4.1941-15 5.3861-15 6.759r-15 V2L1 54 18 Skin ga= tDCr for semi-infinite monoener. cloud src t(Sv/s)/(Bq/=3)1 V2L1 55

1.138z-16 7.690r-16 1.4671-15 2.717R-1S 4.416R-15 6.737r-15 V2L1 56 1.2393-14 2.073E-14 3.1931-14 4.7543-14 7.1083-14 1.0123-13 V2L1 57 1.317Z-13 1.624g-13 2.0893-13 3.030E-13 4.305Z-13 5.922B-13 V2L1 58 RADIONUCLIDE DATA BASZ V2L1 59 1 it 3 (Sre C1) 1.4712+01 2.186E+01 1.7441+01 2.536Z+01 V2L1 60 Decay chain, decay constants and branching fractions V2L1 61, n 3 V2L1 62 6.40320Z-06 .000001+00 .OOOOOE+00 .0001+00 .0001+00 .OOO+.00 V2L1 63 ORIGEN-2 18-group phot/dLi, and ICRP-38 betas (MeV/dis) V2L1 64

.0001+00 .0001+00 .0001+00 . 000+00 .000Z00 .0001.00 V2L1 65

.000Z+00 .0001+00 .0001.00 .0001+00 .0001.00 .0002300 V2L1 66

.000+00 .0001+00 .0001+00 .OOO+00 .0001+00 .0001+00 V2L1 67 5.600Z-03 V2L1 68 ICRP-38 Organ DCxs - Air iner, arnd shine, Inhal/Class V V2L1 69

.0001+00 .0001+00 2.7501-18 .0001+00 .0003.00 .0003+00 V2L1 70

.0001+00 3.310Z-19 .0001+00 .0001Z00 .0001+00 V2L1 71

.0001+00 .000z+00 .0001+00 .00oz+00 .0003+00 .0003.00 V2L1 72

.0003+00 .0001+00 .000X+00 .0008+00 .0003Z00 V2LW 73 1.730E-11 1.730E-11 1.7301-11 1.730Z-11 1.730Z-11 1.730E-11 V2LI 74 1.7301R-11 1.730E-11 .000E+00 .OOOE+00 V2L1 75 2 C 14 (Sre C1) 3.125Z-06 4.723Z-06 3.772E-06 5.4673-06 V2L1 76 Decay chain, decay constants and branching fractions V2L1 77 C 14 V2LI 78 1.38016Z-08 .00000R+00 .000001400 .0001400 .0001+00 .OOOZ+00 V2L1 79 ORSGZN-2 18-group phot/dis, and ICRP-38 betas (MeV/dis) V2L1 80

.000E+00 .0001.00 .0003+00 .000+00 .000E+00 .000OO00 V2L1 81

.OOO00 .000E+00 .0001+00 .000E+00 .0001+00 .OOO+00 V2L1 82

.0001+00 .0001+00 .0001+00 .00OZ+00 .0001E00 .OOO100 V2L1 83 4.940Z-02 V2L1 84

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWQ)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 102 AR EVA 88 ICRP-38 Organ DCTs - Air 4 r, ornd shine, Inhal/Cltas c V2Ll 85 89 2.590Z-19 3.520Z-19 1.530B-19 1.210Z-19 7.060Z-19 2.190Z-19 V2L1 96 90 1.5408-19 2.2408-19 .OOO+00 .000E+00 2.4308-16 V2LI 87 91 2.220E-20 2.5208-20 8.6508-21 7.250Z-21 4.630B-20 1.250E-20 V2L1 88 92 1.0308-20 1.6108-20 .0001.00 .000R+00 7.460Z-20 V2L1 89

(.... etc., for a total of 414 radionuclides .... )

ELISA-2 tLICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUAT1ONS - ENTCE ENO. - Ro1. Version 2.2 May 23,20021 3-Nov-04 PAGE 4 CASR# 1 PNPS AST - MEA- BOUNDING SRC - 24 Mt DECAY - RD VENT RELEASES - LPZ w/Gama XI/O (INSTANTANEOUS RELEASE FROM SOURCE)

LISTI%= OF INPUT DATA PATHWAY OPTION - 3 (CONP. A -- > SITE)

COMPARTMENT As Refueling Level TOTAL FREE AIR VOLUNE (cu ft) - 7.000E+05 FILTERED RECIRCULATION RATE (cfa) a .OOO+00 LEA RATE TO ATMOSPHERE (frac/day) - 9.6008+01 FILTER REMOVAL EFFICIENCIES AND TIME-DEPENDENT MULTIPLIERS FOR RECIRCULATION RATES, LEAM RATES, COMP. A FrOW BETWEEN SPRAYED AND UNSPRAYED AREAS, AND FILTER BYPASS FRACTIONS ARE GIVEN BELOW.

NO. OF DISCRETE TIME VALUES IN INPUT a 8 INTERMEDIATE RESULTS WILL BE PRINTED AT THE FOLLOWING TIMES (hra)l

.OOOO+00 PROBLEM END TIME (hours) w 7.20008+02 RELEASE RATES AND DOSE RATES ARE PRIOR TO TIME-STEP CHANGES, IF ANY.

ONLY EXACT SOLUTION OF THE DIFFERENTIAL EQUATIONS WAS EMPLOYED IN THE ANALYSIS.

A A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Document ID32*5052589-01 A R E VA Prepared by, John N.Hamawi Page 103 ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTzCE eNa. - Rel. Vernion 2.2 May 23,20021 3-Nov-04 PAGE 5 CASIt I MNPg AST - TEA - BOUNDING SRC - 24 RIR DECAY - RB VENT REMASUS - LPZ w/CGa X/Q (INSTANTANEOuS RELEASE FROll SOURCE)

RECIRCULATION, EXRAUST AND INTAKE FILTER REMOVAL EFFTICENCIES (fractions)

COMPARTEENT A RECIRC. COMPARTMENT B RECIRC. COMPARTMENT C RECIRC. EXHAUST TO ATMOSPHERE INTAKE TO COMPART. C NUCL. ---------------------- FORM_____O______FORM__

GROUP FORM 1. FORM 2 FORM 3 YoRH I YORH 2 FORM 3 FORM I FORK 2 FORM 3 FORM I FORM 2 FORM 3 FORM I FORM 2 FORM 3

_____ ------ ------ ------ ______ ------ ------ ______ ------ ------ ------ I------ ------ ------ ------ ------

I .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 2 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 3 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 .0000 USZR-sPECIFIED CLASSIFICATION or RADIONUCLIDES AND INSTANTANEOUS TRACTIONAL RELEASES FROM THE SOURCE (AT TaO)

GROUP I L B N I N T 9 FORM I FORM 2 FORM 3 1 KR XE 1.000z+00 .0001+00 .000Z00 2 BR S I 2.850B-03 2.150Z-03 .000E+00 3 zz .0001+00 .0003+00 .0001+00 ELEMENT ZZ' STANDS FOR THE REMAINING DATA-LIBRARY ELMENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32.5052589-01 Page 104 ARE VA ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTSC8 8NS. - Rel. Version 2.2 Kay 23,20021 3-Nov-04 PACZ 6 CASB#1 PNPS AST - FMA - BOUNDING SRC - 24 HR DECAY - RB VENT RELEASES - LPZ w/Gwrna X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

TIME INTERVAL CONCZNTR. GQAMA DEPOSITION BREATHING

zx5.HIL.r. COMPART. C COMPART. C X/Q X/Q D/Q RATS BYPASS INT.PILTER OCCUPANCY (hourn) (sc/am3) (nec/m3) (1/m2) (W3/s8e) *FRACTION BYPASS YR. FACTOR

.OOOOZ+OO - 5.0000B-01 3.692Z-05 3.551Z-05 .000E+00 3.5005-04 *0005.00 .0008+00 1.000Z+00 5.0000o-01 - 1.0000X+00 3.692Z-OS 3.551Z-05 . 0005+00 3.500X-04 * .000Z+00 .0005+00 1. 0005+00 1.00005+00 - 2.00008+00 3.692Z-05 3.551Z-05 .OOOE+00 3.5005-04 .000Z+00 .0008+00 1.000Z00 2.0000+00 - 8.00008+00 1.915Z-05 1.782Z-05 ,0005+00 3.500B-04 * .0005+00 . 000Z+00 1.0008+00 8.0000z+00 - 2.4000E+01 1.0668-05 9.627B-06 .0005+00 1.8005-04 .0005+00 .0008+00 1.0005+00

2. 4000x+01 - 9.60005+01 4.3395-06 3.7455-06 .0005+00 2.3005-04 .0005+00 .0005+00 1.0005+00 9.6000z+01 - 7.2000E+02 1.1945-06 9.6568-07 .000+00 2.300E-04 . .0005+00 .0008+00 1.0005+00 TIME INTERVAL COMPART A MULTIPLISRS COMPART . B MUtTIPLIBR8 COMPART C MULTIPLIERS FLOW MULT.

(IFAPPLICABLZ) (IF APPLICABLE) (Ir APPLICABLE) SPRAYED AREA (hours) LEAK RAES REC.FILTZR LEAK RATS REC.ILTER INTAKE/23M PEC.FILTER TO UNSPRAYED

.0000+00 - 5.0000Z-01 1. 000Z+00 1. 0005+00 1.0005+00 1.0005+00 1.0005+00 1. 000Z+00 1.o000+00 5.0000Z 1.00008+00 1.000S+00 1.0005+00 1.0005+00 1. OOO+00 1.0005+00 1.0008+00 1.0008+00 1.0000E+00 - 2.00003+00 1.000R+00 1.OOOS+00 1. 0005+00 1.0005+00 1.0005+00 1. OOOZ+00 1. OOOH+00 2.00008+00 - 8.0000Z+00 1.0005+00 1. 0005+00 1.0005+00 1. 000Z+00 1.0008+00 1.0005+00 1.OOO+.00 8.0000E+00 - 2.40005+01 1.000R+00 1. 0005+00 1.0005+00 1. 000S+00 1. 000+00 1. 0005+00 1.0005+00 2.4000Z+01 - 9.60008+01 1. 0005+00 1. 000.+00 1.0003+00 1. 000+00 1.0005+00 1. 000+00 1.0005+00 9.6000Z+01 - 7.2000E502 1.000+00 1. 0005+00 1.*000+00 1.0005+00 1.0001+00 1.000+00 1.0005+00

A PNPS - Radiological Consequences of aDesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWQ Prepared by: John N.Hamawi Document ID32-5052589-01 Page 105 AR EVA 8L1SA-2 [LICENSING & SEVZRE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECH MUM. - Rel. Version 2.2 May 23,20021 3-Nov-04 PAGE 7 CASZ# 1 PUPS AST - FnA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - LPZ w/CGara X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

USER-SPECIFI8D SOURCE INVENTORY NUCLIDX GROUP MCiU NUCLIDE GROUP (cL) NUCLIDE GROUP (CL)

BR 82M 2 7.8920R+01 KR 87 1 1.1750E404 1134 2 3.8150E+04 BR 82 2 2.04203+02 KR 88 1 1.6620R+04 1135 2 3.18201+04 BR 83 2 2.5670Z+03 XR 89 1 2.0960R.04 113614 2 9.44601+03 BR 84H 2 1.32803+02 XR 90 1 2.0810Z+04 1136 2 1.54401+04 BR 84 2 4.7330E+03 1128 2 5.7020R+02 X313114 1 1.905014+02 BR 85 2 5.8150E+03 1129 2 1.7930Z-03 X313314 1 1.05208+03 BR 86 2 4.35608+03 1130M 2 5.40203+02 13133 1 3.41701+04 BR 87 2 9.9210E+03 1130 2 1.38308+03 X313514 1 6.82503+03 BR 88 2 1.13006+04 1131 2 2.71703+04 X3135 1 1.7440Z.04 KR 83M 1 2.5670Z+03 1132 2 2.41103+04 X1137 1 3.0070Z+04 KR 85M 2. 5.88003+03 X133 2 3.4170E+04 13138 1 3.03701+04 XR 85 2. 8.5510E402 1134M 2 4.07403+03 XZ139 1. 2.44703+04 BLISA-2 [LICENSrNG & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECE UNG. - Rel. Version 2.2 May 23,20023 3-Nov-04 PAGE 8 CASE# 1 PNPS AST - YRA - BOUNDING SRC - 24 ER DECAY - RB VENT RELEASES - LPZ W/Gaoo k X/O (INSTANTANEOUS RELEASE FROM SOURCE)

SOURCE INVENTORY FOLLOWING 2.4003+01 HOURS OF RADIOACTIVE GROWTH AND DECAY PRIOR TO RELEASE NUCLrDx GROUP (Ci) NUCLIDE GROUP (CL) NUCLIDE GROUP (CL)

BR 82 2 1.2761Z+02 BR 89 3 9.0150Z-0i X813314 1 9.4669Y.+02 BR 83 2 2.43523+00 1128 2 2.5419E-15 X1133 1 3.28699+04 BR 84 2 1.10573-10 1129 2 1.79303-03 X3135M 1 4.11603+02 XR 83H 1 9.44453+00 11301 2 3.69633-46 XB135 1 9.60503+03 KR 851 1 1.45053.02 1130 2 3.61473+02 X1338 1 7.7776Z-27 KR 85 1 8.55013+02 1131 2 2.4926E+04 C8135 3 6.60143-06 KR 87 1 2.4729E-02 X132 2 1.7419E+01 CS137 3 7.29873-03 KR 8B 1 4.74433+01 1133 2 1.5357E+04 CSi38 3 9.23373-10 RD 87 3 3.62973-11 1134 2 2.18963-04 C8139 3 1.41353-43 RB 88 3 5.29251+01 1135 2 2.56973+03 BA137M 3 6.90453-03 R1B 89 3 1.67311-25 XE131M 1 1.96063+02 BA139 3 1.2700Z-03

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589l01 Page 106 ARE VA ZL!SA-2 (LICENSING & SSVBRE ACCIDENT RADIOLOGICAL EVALUATIONS - ENwECE ENz. - Rel. Version 2.2 May 23,20021 3-Nov-04 PAGE 9 CASE# 1 pNPg AST - ?HIA - BOUNDING SEC - 24 HR DECAY - RB VENT RELEASES - LPZ vI~anca XIQ (INSTANTANZOUS RELEASE FROM SOURCE)

T - .00008+00 hrx DISTRIBUITION OF RADIOACTIVITY NUCLIDE CONPARTM. CH=M-SPRAY REC.FILTER COMPARTN. REC. FILTER ZXR.FILTBR OFFSITE A IN COMP. A IN COMP. A B iN COMP. B TO ATMOSP. GROUND DEP (Ci/m3) (Ci) (Ci) (CL/m3) (Ci) (Ci) (Ci/fti2)

BR 82 3.219Z-0S .000+00 .000Z+00 .0003+00 .0003+00 .0003+00 .000+00 9R 83 6.143Z-07 .0003+00 .000B+00 .0003+00 . 000Z+00 .0003+00 .0003+00 BR 84 2.789Z-17 .0003+00 .0003+00 .000R+00 .0003+00 .0003.00 .0003+OO KR 83M 4.7653-04 .000+00 .00OZ+00 .0003+00 .0003+00 .0003+00 .0003.00 KR 85M 7.318Z-03 .0003+00 .0003+00 .000B+00 .0003+00 .0003+00 .00O0+00 KR 85 4.3143-02 .0003+00 .0003+00 .0008+00 .0003.00 .OOOR00 .0003+00 KR 87 1.248Z-06 .000+00 .0003+00 .OOO+00 .0003+00 .0003+00 .0008+00 KR 89 2.394Z-03 .0008+00 .000.+00 .0008+00 .0003+00 .0003+00 .000+00 X128 6.4123-22 .0003+00 .0008+00 .OOO+00 .0003.00 .0003+00 .0003+00 X129 4.523B-10 .000+00 .0003+00 .000E+00 .0003.00 .0003+00 .0003+00 1130M 9.324R-53 .0003+00 .0003+00 .0003+00 .0003+00 .000+00 .0003+00 1130 9.118B-05 .0003B00 .0003+00 .000+00 .OOOZ+00 .000+00 .000o+00 1131 6.288Z-03 . OOO+00 .000E+00 .OOO+00 .0003.00 .0003+00 .000B+00 1232 4.394E-06 .0003+00 .000B+00 .0003+00 .0003+00 .0003+00 .0003+00 1133 3.874Z-03 .0003+00 .0003+00 .000+00 .0003+00 .0003.00 .000B+00 1134 5.523E-11 .000Z00 .000E+00 .0003+00 .0003+00 .000+00 .000+o0O 1135 6.4823-04 .OOO+00 .000E+00 .000R+00 .0003+00 .000B+00 .000R+00 XZ131M 9.891Z-03 . 000Z+00 .0003+00 .OOO+00 .0003400 .0003+00 .0003+00 XB133M 4.7763-02 . OOO0+00 .0003+00 .0003+00 .0003+00 .000+.00 .000B+00 X3133 1.658E+00 .0ooo+00 .OOO+00 .OOO+00 .000Z+00 .0003+00 .000E+00 X31351 2.077Z-02 .OOO00 .0003+00 .OOO+00 .0002+00 .000B+00 .0003+00 XZ135 4.8463-01 .000o+00 .0003+00 .000+00 .0003+00 .000B+00 .OOO3.00 XE138 3.924Z-31 .0ooo+00 .OOO+00 .OOO+00 .000B+00 .0003+00 .000B+00 TOTALS GROUP 1 2.2753+00 .000R+00 .0003+00 .0003+00 .0008+00' .0003+00 .0003+00 GROUP 2 1.0943-02 .000+00 .OOO+00 .000R+00 .000+00 .0003+00 .OOO+00 GROUP 3 .0003+00 .OOO.00 .00OZ+00 . 000X+00 .OOO+00 .0003+00 .000+00 GRND.TOT 2.2835+00 .000+00 .0008+00 .0003+00 .000Z+00 .0003+00 .00O0+00 THE COMPARTMENT VOLUMES (A AND B) IN THIS TABLE AREt 1.9828+04 .0003+00 (W3)

A A R ABased EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32.5052589-01 Page 107 ELISA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ZNSZCE ZNG. - Ro1. Votsion 2.2 May 23,20021 3-Nov-04 PAGE 10 CASE1 1 PNPB AST - M2A - BOUNDING SRC - 24 BR DECAY - RD VENT RELEASES - LPZ wIGa=a X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

T = .0000X+00 hra RELEASE RATES TO ATMOSPHERE, INTERVAL RELEASES FROM .00003+00 TO .0000E+00 hro, CUMULATIVE RELEASES FROM 0.0 TO .00003+00 hr., AND RADIOACTIVE-CLOUD CONCENTRATIONS WITHOUT DECAY IN TRANSIT WITH .0003+O0 hra IN-TRANSXT DECAY REL. RATE INTRV REL CUML. REL CLOUD CONC REL. RATE INTRV REL CUML. REL CLOUD CONC NUCLIDE (Cl/hr) (CL) (Ci) (Cim3) (Cl/hr) (CL) (CL) (Ci/n3)

BR 82 2.552E+00 .oooe000 .000+00 2.617E-08 2.552Z+00 .0003+00 2.617E-08 BR 83 4.870Z-02 .000+00 .oooe+00 4.9953-10 4.870B-02 .000K.00 .000+00 4.9953-10 BR 84 2.2113-12 .0003.00 .0003+00 2.268B-20 2.21tZ-12 .0003+00 .0003+00 2.268B-20 KR 83M 3.778E+01 .OOO00 .000.+00 3.8743-07 3.7783+01 i0003.00 .00O+00 3.874E-07 KR 85M 5.802E+02 .OOOE+00 .OOO300 5.9503-06 5.8023+02 .0003:.00 .0003+00 S.9503-06 KR 85 3.4203+03 .0003.00 .0003.00 3.5073-05 3.4203+03 .0003.00 .0003+00 3.507N-05 KR 87 9.8923-02 .0003.00 .0003+00 1.0243-09 9.8923-02 .0003.00 .0003400 1.014B-09 KR 88 1.898.+02 .0003.00 .OOOZ+00 1.9463-06 1.898+.02 .,0003+00 .000oo00 1.946R-06

-1128 5.0843-17 .0003+00 .OOO300 5.2143-25 5.0843-17 .0003.00 .0003+00 5.2143-25 1129 3.5863-OS .0003+00 .0003+00 3.6783-13 3.5863-OS .000Z+00 3.6783-13

.0003.00 1130M 7.3933-48 .0003+00 .0003.00 7.5823-56 7.3933-48 .000z+00 7.5823-56

.000X.00 1130 7.229+00 .OOO3+00 .0003+00 7.414E-08 7.2293+00 .0003+00 7.414E-08

.0003+00 1131 4.9853+02 .OOO+00 .0003Z00 5.1133-06 4.9853+02 .OOOE+00 5.113E-06

.. 0003+00 1132 3.4843-01 .0003.00 .000X+00 3.5733-09 3.4843-01 .OOOE+00 3.573z-09

.0003400 X133 3.0713+02 .0003+00 .0003+00 3.150E-06 3.0713+02 .0003+00 3.150E-06

.0003+00 1134 4.3793-06 .000+00 .0003+00 4.4913-14 4.379E-06 .OOO+300 4.4913-14

.0003.00 1135 5.1393+01 .000oo00 .0003.00 5.2713-07 5.139E301 .OOOE+00 5.27 1-07

.000H+00 XZ13 iN 7.843.+02 .0003+00 .000+00 8.0433-06 7.843E+02 .000+00 8.*043-06

.0003.00 XE133M 3.787E+03 .OOO+00 .000OE00 3.8843-05 3.7873+03 .0003+00 3.8843-05

'.0003400 Xg133 1.315e+05 .0003+00 .0003.00 1.3483-03 1.3153+05 .000+00 1.3483-03

.0003+00 XB135M 1.646E+03 .000+.00 .000+00 1.688Z-05 1.6463+03 .000+00 1.6883-OS XB135 3.8428+04 .000R.00 .OOO300 3.9403-04 3.842+.04 .0003+00 .000+00 3.940B-04 X 138 3.111B-26 .000+.00 .0OOO+00 3.1913-34 3.1113-26 .. 0003:.00 .OOO+00 3.1913-34 I

TOTALS GROUP 1 1.8033+05 .OOO+00 .0003+00 1.849E-03 1.8033+05 . ooo0000 .0003+00 1.849B-03 GROUP 2 8.6723+02 .0003+00 .0008+00 8. 8943-06 8.6723+02 .0003+00 .0003+00 8.8943-06 GROUP 3 .oooe+00 .000e+00 . OOO+00 .0003+00 .0OOO+00 .0003400 .00oz+00 .OOO+00 aRND.TOT 1.812R+OS .000o+00 .0003+00 1.858E-03 1.8123+05 . ooo000 .0003+00 1.858B-03 NOTEs THE ATMOSPHERIC CONCENTRATION OF RADIOACTIVITY I8 BASED ON A DIspERSION FACTOR (XIQ) OF 3.6923-05 (sec/m3)

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altem alive Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 AR EVA Page 108 ZLISA-2 ELICINSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECR ENO. - Rel. Vergion 2.2 May 23,20021 3-Nov-04 PACE 11 CAS# I P9PS AST - FHA - BOUNDGNG SRC - 24 RR DECAY - RB VENT RELEASES - LPZ W/Gam^a X/Q (INSTANTANIOUS RELEASE FROM SOURCE)

T a .0000E+00 hra EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE FROM .00001+00 TO .00001+00 hre) 8eta Air Beta Air Ganma Air camia Air Tot. Skin Tot. skin Thyroid Thyroid Zff D.E. 1ff D.S.

DOSE RATE INTVL DOS DOSE RATE rNTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE IWXVL DOS NUCLIDE (rad/hr) (rad) (rad/hr) (rad) (rea/hr) (rem) (rem/hr) (rein) (rem/hr) (rem)

BR 82 6.471Z-06 .0001+00 5.9118-05 . 0001+00 5.172B-05 .0001*00 4.359Z-05 .000H+00 4.359Z-05 .0001*00 BR 83 2.854E-07 *.000+00 3.194Z-09 .*000+00 1.2301-07 .0001+00 2.432B-09 2.4441-09 .0001400 BR 84 4.9573-17 .000x+00 3.467E-17 .0001+00 5.560B-17 .0003.00 2.7608-17 .0003+00 2.7343-17 .000R*00 KR 83M 2.667z-05 . 000z+00 8.537B-07 .0001+00 1.779Z-07 .000Z*00 3.1921-09 .0003*00 7.445B-09 .0001+00 KR 85M 2.702B-03 .0001+00 8.0463-04 .0001.00 1.749Z-03 .00Z000 5.588z-04 .000z+00 5.7021-04 .000Z+00 KR 85 1.563B-02 .OOO100 6.6241-05 .000.+00 6.165Z-03 .0001+00 5.302Z-05 .0001.00 5.3471-05 .0001*00 KR 87 2.3891-06 .0001+00 6.87BZ-07 .0001+00 1.828B-06 .0001+00 5.367B-07 .0001*00 5.354U-07 .0001+00 KR 88 1.2618-03 .0001+00 3.253Z-03 .OOO+100 3.387Z-03 .0008+00 2.5681-03 .0001+00 2.5431-03 .0001+00 RB 87 .0003.00 .0005+00 .000Z+00 .OOO+.00 .0001.00 .0001+00 .0001+00 .0001+00 .0001+00 .0001+00 RB 88 .0001.00 .0005.00 .00O0100 .000E+00 .0003+00 .0001+00 .0001+00 .0001+00 .00O0100 .OOO+.00 1128 6.935Z-22 .0001+00 3.799B-23 .0001+00 3.724B-22 .0001+00 2.7591-23 .0001.00 2.7798-23 .OOO+00 1129 4.1731-11 .0001400 7.760Z-12 .0001+00 5.236B-12 .0001+00 1.819B-12 .0001+00 1.7908-12 .OOO+100 11303 .0003+00 .0ooo0oo 7.700E-54 .000Z+00 6.251Z-54 .0001+00 .0001+00 .0003+00 .0001+00 .OOO+00 1130 3.919Z-05 .000X+00 1.3579-04 .0001+00 1.2981-04 .0001Z00 9.079Z-05 .0001+00 9.879Z-05 .OOO+.00 1131 1.743E-03 .0001400 1.6671-03 .OOO+00 1.975Z-03 .00O1400 1.186B-03 .0001+00 1.192Z-03 .OOO+00 1132 3.147E-06 .o000z00 6.9731-06 .OOO+100 7.2871-06 .0001+00 5.126e-06 .000+00 5.126B-06 .OOO+00 1133 2.3008-03 .000oo00 1.635S-03 . 000Z00 2.392Z-03 .0003.00 1.182B-03 .0001+00 1.186B-03 .000Z+00 1134 4. 970Z-11 .000o+00 1.009Z-10 .0001+00 1.0851-10 .0001+00 7. 4e0-11 .0001.00 7.4801-11 .0001+00 1135 3.4401-04 . 000z+00 7.1003-04 .0001400 7.552-04 .0003+00 5.4093-04 .0008+00 5.389B-04 .0001+00 XZ131M 2.057Z-03 .0001.00 1.3821-04 . 000Z+00 5.1341-04 .0005+00 4.029Z-05 .0005+00 4.008B-05 .0001400 XB133M 1.328Z-02 .000Z+00 1.3821-03 .0001+00 5.342U-03 .0003+00 6.7661-04 .000+.00 6.8161-04 .000Z00 XZ133 3.2541-01 .OOO+100 5.2411-02 .0001+00 8.778B-02 .0001+00 2.608Z-02 .0001+00 2.695-02 .0001+00 XB135X 2.9288-03 . 000+00 6.239B-03 .0008+00 6.4741-03 .OOO+00 4.4131-03 .000z+00 4.4131-03 .OOO+00 XZ135 2.223Z-01 .0001+00 8.355Z-02 .0001.00 1.610B-01 .OOO+00 5.956B-02 .0001+00 6.0078-02 .OOO+00 XZ138 3.816g-31 .0001+00 3.070-31 .000+.00 4.4421-31 .OOO+00 2.358B-31 .0001+00 2.3581-31 .0001+00 CS135 .000o400 .0001+00 .0001.00 .0001+00 .0008+00 .000+.00 .000+.00 .0001+00 .0001+00 .0001.00 C8138 .0ooo000 .0001+00 .OOOE+00 .0001+00 .000Z+00 .0001+00 .0001+00 .OOO+OO .0001.00 .0001+00

A PNPS - Radiological Consequences of a Oesign-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 109 AR EVA ELXSA-2 rLICHNSINo & SEVERE ACCIDENT RADIOLOGICAL IVALUATIONS - ENTECH ENG. - Rel. Version 2.2 May 23,20021 3-Nov-04 PAGE 12 CAS9# 1 PNPS AST - TRA - BOUNDING 8RC - 24 ER DECAY - RB VENT RELEA8ZS - LPZ W/Gasa X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

T a .0000z+00 hr. EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE FROM .OOOOE+00 To .0000Z+00 hrn)

Beta Air Beta Air Gama Air Camn Air Tot. Skin Tot. Skin GonaOd Gonads Breast Breast DOSE RATE INTVY DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVL DOS DOSE RATE INTVI DOS (rad/hr) (rad) (rad/hr) (rad) (r /hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 5.856Z-01 .000,+00 1.4793-01 .0001+00 2.724Z-01 . OOO+OO 9.503E-02 .0001+00 1.103B-01 .000Z+00 GROUP 2 4.4363-03 .OOOZ+00 4.214E-03 .0001+00 5.3111-03 .000+00 2.992Z-03 .0001+00 3.4171-03 .000+00 GROUP 3 .000Z+00 . 0001Z00

000E+00 .0001+00 .000+00 .0001+00 .OOO1.00 .0001+00 .OOO+00 .000E+00 GRND.TOT 5.900Z-01 .000Z+00 1.521E-01 .oooe+00 2.7771-01 .0001+00 9.802Z-02 .0001+00 1.1371-01 .0001+00 CUM. TOTAL FROM T-0 .0001+00 .0oooz00 .0001+00 .000Z+00 .0001+00 Lungs Lungs R.Marrow R.Marrow Bone our Boae Sur Thyroid Thyroid Remaindr Remaindr DOSE RATE INTVL DOS. DOGE RATE INTVL DOS DOSE RATE rmrVL DOS DOSE RATE rNTVL DOS DOSE RATE IrTVL DOS (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 8.785Z-02 .OOO+00 8.023B-02 .000Z+00 2.326E-01 .0001+00 9.3961-02 .000R+00 8.362Z-02 .000+00 GROUP 2 2.980Z-03 .OOOE+OO 2.8821-03 .0001+00 5.222E-03 .000Z+00 3.0S6Z-03 .000B+00 2.8441-03 .000+00 GROUP 3 .0001+00 .000E+00 .000o+00 .0001+00 .0001+00 .0003+00 .0001+00 .000+00 .000+00 .000B+00 GRND.TOS 9.083Z-02 .000+00 8.311Z-02 .000R+00 2.379E-01 . 000+00 9.702.-02 .000B+00 8.647B-02 .OOOZ+00 CUM. TOTAL FROM T-0 .0001+00 .0001+00 .000B+00 .000R+00 .000+00 Zff D.E. Rff D.E. TID Thy TID Thy RO1109WB RG11O9WB DOSE RATE IVL DOS DOSE RATE ILqTVL DOS DOSE RATE INTVL DOS (rem/hr) (rem) (rem/hr) (re) (rvn/hr) (rem)

GROUP 1 9.532E-02 .000o+00 .000R+00 .0003+00 1.3571-01 .0008+00 GROUP 2 3.0658-03 .0003+00 .0003+00 .000B+00 3.9603-03 .000E+00 GROUP 3 .000E+00 .oooe+00 .0001+00 .000+00 .OOOE+00 .0OOOZ+0O ORND.TOS 9.83ez-02 .OOO+00 .000o+00 .OO0+00 1.397E-01 .000+00 CUM. TOTAL FROM T=O .OOOZ+00 .000B+00 .000X+00

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 110 AR EVA ELISA-2 (LICENSZNQ & SEVERZ ACCIDENT RADIOLOGICAL EVALUATIONS - ZNSECH SNM. - Rol. Version 2.2 May 23.20021 3-Nov-04 PAGM 13 CASE# I PNPS AST - FHA - BOUNDING SRC - 24 HR DECAY - RB VENT RELEASES - LPZ w/Gaba X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

S w .00003+00 hre RADIATION EXPOSURE DUE TO INHALATION (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (INTERVAL DOSES ARE FROM .0000Z+00 T0 .00003.00 hro)

Thyroid Thyroid Bff D.E. 8ff D.E.

DOSE RATE rNTVL DOS DOSE RATE INTVL DOS NUCLTDZ (rem/hr) (rem) (rem/hr) (rem)

BR 82 2.514K-05 .0001+00 5.0403-05 .0003+00 BR 83 2.6553-09 .0003+00 5.612B-08 .0003+00 BR 84 3.2993-19 .000.+00 2.760Z-18 .0003+00 KR 83M .0008+00 .000z+00 .0003+00 .0003+00 KR 85M .0003+00 .0003.00 .0003+00 .0003+00 KR 85 *000R+00 .0003+00 .0003+00 .000H+00 KR 87 .000.+00 . 000300 .0003+00 .OOOE+00 KR 88 . 0003+00 .000X+00 .0003.00 .00013.00 RB 87 .0003.X00 .0003+00 .0003S+00 .0003+00 RB 88 .0003+00 .0003.00 .0003+00 .0003.00 1128 1.2983-22 .0003+00 3.1113-23 .0003+00 x129 2.61SX-06 .0003+00 8.0413-08 .0003+00 1130O .0003+00 . 0003+00 .0003+00 .0003+00 1130 6.8783-03 .000+00 2.4688-04 .0003+00 1131 6.9603+00 .0003+00 2. 193-01 .0003+.00 1132 2.898K-05 .0003+00 1.7163-06 .0003+00 1133 7.137Z-01 .0003+00 2.3203-02 .0003+00 X134 6.030B-11 .OOO+00 7.4333-12 .0OOOE00 I135 2.0793-02 .oooe000 8.1583-04 .000z+00 XE131M .000.E00 .0003.00 .0003+00 .0003.00 X3133M .0003+00 .0003+00 .0003+00 .0003+00 X%133 . 000300 . 000+.00 .0OOO+00 .0003+00 XZ135M .000Z+00 .0003+00 .0003+00 .0003.00 XE135 .0003+00 .0003+00 .0003.00 .000.E00 XB138 .0 00+00 .000t00 .0003+00 .0003+00 C9135 .0003+00 .0003+00 .0003+00 .0003+00 C8138 .0003+00 .000Z00 .0003z00 .0003+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 111 ARE VA ELISA-2 (LICENSING & SEVERB ACCIDENT RADIOLOGICAL EVALUATIONS - ENTECR BNO. - Rol. Vernion 2.2 May 23,20021 3-Nov-04 PAGE 14 CASE* 1 PNP8 AST - FMA - DOUNDINO SRC - 24 RR DECAY - RB VENT RELRA8SE - LPZ w/Gamma X/Q (INSTANTANIOVS RELEASZ FROM SOURCE)

S .OO00E+00 hra RADIATION EXPOSURE DUE TO INHALATION (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR (IN=ERVAL DOsZs ARE FROM .00001+00 TO .00001+00 hra)

Gonad. Gonads Breast Breast DOSB RATE INTVL DOS DOSE RATE INTVL DOS (rem/hr) (rem) (rem/br) (rem)

GROUP 1 . 00014.00 .0003+00 .000H+00 .0001+00 GROUP 2 9.6163-04 . 0003+00 2.4101-03 .0003+OO GROUP 3 .0001+00 . 000+00 .0001+00 . 0003+00 ORND.TOT 9.6161-04 .0003+00 2.4101-03 .000o+oo CUM. TOTAL FROM T-0 .000E100 .000oo00 Lungs Lungs R.Marrow R.Marrow Done Sur Bone Sur Thyroid Thyroid Remaindr Remaindr DOSE RATE INTVL DOS DOSE RATE INTVL DOg .DOSZ..RATE INTVL DOS DOSE RATE rNTVL DOS DOSE RATE IZTVL DOS (rem/hr) (rem) (rem/br) (rem) (rem/hr) (rem) (rem/br) (rem) (rem/hr) (rem)

GROUP 1 .000E+00 .0001+00 .0001S+00 .0003+00 .0003.00 .0003+00 .0001+00 .0001.00 .0003+00 .000Z+00 GROUP 2 2.920Z-02 .0001+00

. OOON+OO 1.9891-03 .0001+00 1.823E-03 .0001+00 7.7011+00 .0001.00 2.832Z-03 .0001+00 GROUP 3 .0001+00 .0001+00 .0001+00 .000E+00 .000z+O0 .000O+00 .0001+00 .0001+00 .0003:+00 .000E+00

.OOON+OO GRND.TOT 2.920Z-02 .0003+OO 1.989Z-03 .0001+00 1.8233-03 .0001+00 7.701E+00 .0001+00 2.8321-03 .OOO+00 CVM. TOTAL FROM TaO .0001+00 .000+00 .000Z+00 .0001+00 .OO0+0O Xff D.E. Xff D.E. TID Thy TID Thy DOSE RATE INMVI DOS DOSE RATE INSTV DOS (rem/hr) (rem) (rem/hr) (rem)

GROUP 1 .000+OO .0001+00 .000E+00 .000+00 GROUP 2 2.3628-01 .0003+00 1.120E+01 .0008+00 GROUP 3 .OOO+00 .0001+00 .000E+00 .000E+00 GRND.TOT 2.362Z-01 . OO0O+OO 1.1201+01 .0001+00 CUM. TOTAL FROM TO0 .000R+00 . OOOO+00

A ABased PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident on the Alternative Source Term Methodology (2038 MWt)

Document ID32-5052589-01 A R EVA Prepared by: John N.Hamawi Page 112 ZL18A-2 (LICENSING & SEVERE ACCIDENT RAD!OLOGICAL EVALUATIONS - ENTEC8 MNM. - Rol. Version 2.2 May 23,2002] 3-Nov-04 PAGE 15 CASE# 1 PNPS AST - FRA - BOUNDING SRC - 24 HR DECAY - RD VENT RELEASES - LPZ W/Gaema X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

SUMMARY

TOTAL RADIATION EXPOSURES (AIR IMMERSION PLUS IMNALATION) (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR Beta Air Beta Air Beta Air GCama Air Gemma Air Goms Air Tot. Skin Tot. Skin Tot. Skin DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rad/hr) (rad) (rad) (rad/hr) (rad) (red) (rem/hr) (rem) (rem)

.OOOO300 5.900R-01 .0003+00 .000Z+00 1.521-01 .0003+00 .0003+00 2.777E-01 .0003+00 .0003+00

5. 00003-01 8.097Z-02 1.2783-01 1.2783-01 2.2138-02 3.317Z-02 3.3173-02 3.9423-02 6.0453-02 6.0458-02 1.0000.E00 1.267Z-02 1.8043-02 1.458Z-01 5.1433-03 5.4813-03 3.8653-02 7.809E-03 9.3193-03 6.9773-02 2.0000Z+00 2.1693-03 4.638E-03 1.505Z-01 2.3823-03 3.0813-03 4.1733-02 2.8153-03 4.0373-03 7.381Z-02 8.0000E+00 5.7983-04 4.713Z-03 1.552Z-01 6.300E-04 5.2463-03 4.6973-02 7.4663-04 6.205E-03 8.002E-02 2.40003+01 8.0493-05 2.737Z-03 1.579Z-01 6.6523-05 2.6743-03 4.9653-02 8.160Z-05 3.2223-03 8.3243-02 9.6000R+01 1.2323-06 5.3273-04 1.5858-01 1.7193-07 2.7673-04 4.993Z-02 3.4193-07 3.666B-04 8.360B-02 7.20003+02 4.270B-09 1.8903-05 1.585R-01 2.412E-10 1.7593-06 4.9933-02 1.041Z-09 4.820B-06 8.361E-02 Gonads Gonads Gonads Breast Breast Breast Lungs Lungs Lungs DOSE RATE INTVL DOS CUM. DOSE DOSE RATE .ISrVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE S (hours) (rem/hr) (rem) (rem/hr) (rem) (ren) (rem/hr) (rem) (rem)

.000000Z+ 9.898E-02 .0003+00 .OOOZ300 1.1623-01 .0003+00 .000E+00 1.200E-01 .0003+00 .0003+00 5.0000Z-01 1.447E-02 2.1603-02 2.160R-02 1.6953-02 2.5353-02 2.535E-02 1.739Z-02 2.6222-02 2.622Z-02 1.00003+00 3.4463-03 3.6113-03 2.5223-02 3.997Z-03 4.2173-03 2.9568-02 3.8173-03 4.2343-03 3.0453-02 2.00003+00 1.6483-03 2.1063-03 2.732Z-02 1.9888-03 2.424E-03 3.199E-02 1.631Z-03 2.1783-03 3.2633-02 8.00003+00 4.358E-04 3.632E-03 3.0953-02 4. 9903-04 4* 158Z-03 3.6143-02 4.289z-04 3.577Z-03 3.621B-02 2.4000E+01 4.5533-05 1.8443-03 3.2803-02 5.225E-05 2.1138-03 3.826Z-02 4.4553-05 1.811Z-03 3.802Z-02 9.60003+01 9.1443-08 1.8463-04 3.2988-02 1.1093-07 2.1303-04 3.8473-02 7.583E-08 1.7813-04 3.8203-02 7.20002.02 8.219R-11 8.299Z-07 3.2983-02 1.0838-10 1.0273-06 3.8473-02 4.8023-ll 6.394R-07 3.820Z-02 R.Marrow R.MarrOw R.Karrow Bone Sur Bone Sur Bone Sur Thyroid Thyroid Thyroid DO8B RATE INrV8.DOS CUM. DOSE DOSE RATE INTVL DoS CUM. DOSE DOSE RATE IMVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

.00003400 8.510Z-02 .0003+00 .000E+00 2.397B-01 .0003+00 .000Z+00 7.798Z+00 .OOO+00 .OOO+00 5.0000Z-01 1.255B-02 1.8603-02 1.8603-02 3.428B-02 5.2123-02 5.2123-02 1.0533+00 1.6843+00 1.6843+00

1. 00003.00 3.1083-03 3.170B-03 2.177Z-02 7.3413-03 8.2843-03 6.0403-02 1.436E-01 2.2793-01 1.9123+00 2.00003+00 1.557Z-03 1.9563-03 2.3738-02 3.0293-03 4.1013-03 6.4513-02 4.226Z-03 3.6463-02 1.948Z+00 8.00003+00 4.1183-04 3.4353-03 2.7163-02 7.9913-04 6.646E-03 7.1153-02 4.4333-04 4.0253-03 1.9523.00 2.40003401 4.2603-05 1.737Z-03 2.8903-02 8.549E-05 3.4042-03 7.456Z-02. 4.619Z-05 1.8743-03 1. 9543+00 9.60003+01 6.331Z-08 1.6853-04 2.907Z-02 2.723B-07 3.6633-04 7.492B-02 8.632E-08 1.8613-04 1.954R+00 7.2000Z+02 4.0892-11 S.2943-07 2.907Z-02 1.9063-10 2.4153-06 7.493Z-02 7.032B-11 7.6503-07 1.9543+00

A PNPS. Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 113 AR EVA ELISA-2 [LICENSINO & SEVERE ACCIDENT RADIOLOOICAL EVALUATIONS - =MNCH ZNO. - Rel. Version 2.2 May 23,20021 3-Nov-04 PAGE 16 CA8Z 1 PNPS AST - FHA - BOUNDING 8RC - 24 RR DECAY - Re VENT RELEASES - LPZ w/vG--X XQ (INSTANTANEOUS RELEASE FROM SOURCE)

SUMMARY

TOTAL RADIATION EXPOSURBS (AIR I2mZRSI0N PLUS INHALATION) (CONTINUOUS OCCUPANCY)

OUTDOOR RECEPTOR Remindr Rmindr Reoaindr 1ff D.e. Zff D.E. Zff D.E. TID Thy TID Thy TID Thy DOSE RATE INTVL DOS CUM. DO8S DOSE RATE INTVL DOS CUM. DOSE DOSE RATE INTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem) (rem/hr) (rem) (rem)

. OOOOZl00 8.9301-02 .0001.00 .0001.00 3.346E-01 0001+00 .0001400 1.1201+01 .0001+00 .000+.00 5 00001-01 1.311B-02 1. 9511-02 1. 9511-02 4.629Z-02 7.2493-02 7.2493-02 1.5108+00 2.4181.00 2 4183+00 1.0000R+00 3.174E-03 3.2891-03 2.280B-02 7 767E-03 1.0491-02 8.298Z-02 2 0351-01 3. 259-01 2.7441+00 2.00001+00 1.3483-03 1.964E-03 2.476E-02 1.757Z-03 3.1898-03 8.6171-02 3 696B-03 4.9843-02 2.7941.00 8.00001400 4.0931-04 3.413R-03 2. 8178-02 4. 4403-04 3.7111-03 8.9881-02 6.907B-14 4.7833-04 2.7951+00 2.4000z+01. 4.2501-05 1.7293-03 2.990Z-02 4. 6311-05 1.8788-03 9.1763-02 2.8558-42 4.9353-15 2.795E+00 9.60001+01 7.1611-08 1.6981-04 3.007Z-02 8 g868-08 1.870Z-04 9.1951-02 .00o0400 3.701Z-43 2.7951+00 7.20003.02 4*874E-11 6. 103e-07 3. 007Z-02 6.9961-11 7.824Z-07 9.1953-02 b000R+00 .0001+00 2 .795E+00 Rfl0O9Wn RO1109ND RO1109WB DOSE RATE 2NTVL DOS CUM. DOSE T (hours) (rem/hr) (rem) (rem)

.0000E+00 1.397Z-01 .0001+00 .0003+00 S.0000E-01 2.0261-02 3.0401-02 3.0403-02

1. 00001+00 4.737Z-03 5. 025Z-03 3.5433-02 2.0000E+00 2.2163-03 2.8563-03 3.8283-02

8. 0000E+00 5.8613-04 4.8813-03 4. 3173-02 2.4000E+01 6. 168E-05 2.4851-03 4.565Z-02 9.60001+01 1.4571-07 2.5443-04 4.591B-02 7.20001+02 1. 007Z-10 1.272Z-06 4.591B-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Document ID32-5052589-01 ARE VA Prepared by: John N.Hamawi Page 114 ELISA-2 (LICENSING A SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS - BNTZCH sNm. - Rol. Version 2.2 May 23,20021 3-Nov-04 PAGE 17 CASE# 1 PNPS AST - FRA - BOUNDING SRC - 24 RR DECAY - RB VENT R8LZASES - LPZ w/aama X/Q (INSTANTANEOUS RELEASE FROM SOURCE)

OVERALL

SUMMARY

- TOTAL RADIATION EXPOSURES (AS APPLICABLE) FOR SCENARIO DURATION (7.2000R402 bra)

CONTINUOUS OCCUPANCY RZCEPTOR/ORSAN COMPARTMENT A COMPARTMENT B COMPARTMENT C OFFSITE RECEP.

(Hemispher) (Spherical) (Spherical)

Beta Air (rad) .OOO+O0 .0001+00 .0001.00 1.585Z-01 Gaime Air (rcd) .0001+00 .0001+00 .0001+00 4.993R-02 Tot. skin (rem) .0008+00 .0001+00 .000R00 8.361g-02 (Beta Cont. (k)] t .001 I .001 I .OOJ t 52.34]

Gonads (rem) .0001+00 .0003+00 .0001.00 3.2988-02 Breast (rem) .0001+00 .000+00 .00O0+00 3.8471-02 Lungs (rem) .OOO+00 OOO+00 .0001+00 3.8201-02 (Inhalation (%)] 1 .00) .001 t .001 t 19.321 R.Marrow (rem) .0001+00 .0001.00 .000X.00 2.907z-02 Bone Sur (rem) .0001+00 .0001+00 .OOO00 7.493Z-02 Thyroid (rem) .0003.00 .OOO+00 .0001+00 1.9541+00 tlnhalation (%)] t .001 C .001 t .001 C 98.331 Remaindr (rem) .0001+00 .000.+00 .0001+00 3.007R-02 Rff D.E. (rem) .OOOE+OO .0001.00 .000Z+00 9.195-02

[Inbalation (%)] C .001 I .001 I .001 1 64.121 TID Thy (rem) .0001+00 .000R+00 .000io00 2.7951+00 RGl1O9WB (rem) .OOO+00 .0001+00 .0001+00 4.5911-02 The Dose Conversion Factors (DCXF) employed by ELISA-2 are from EPA 520/1-88-020 and EPA 402-R-93-081 (Federal Guidance Reports 11 and 12), except for TID Thy and RG1109WB, which are en followas TID Thy - Classical thyroid inhalation done based on the TID-14844 DCFe (iodines only)

R01109WB - Classical whole body immersion dose based on the Reg. Guide 1.109 DCrs (nobles and halogens only)

The beta dose to air is for nmersion in an infinite cloud.

The skin dose includes contributions from gamma radiation (finite cloud), beta radiation (semi-infinite cloud) and ground contamination. The skin beta-contribution percentages exclude ground contamination.

Finite-cloud correction, if any, L nuclide specific.

~*****~*- END OF THIS CASE ***-

5.*.-**-**.* END OF ANALYSIS ***

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Harnawi Document ID32-5052589-01 Page 115 ARE VA RADTRAD Run Case #A - Nuclide Inventory File

A PNPS- Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 116 AR EVA Nuclide Inventory Name:

Pilgrim -FRA - Bounding Source Term - 151 Rupured rods Power Level:

0.1211E+02 Nuclides:

60 Nuclide 001:

Co-58 7

0.6117120000E+07 0.5800E+02 0.0 none O.OOOOE+00 none O.OOOOE+OO none O.OOOOE+00 Nuclide 002:

Co-60 7

0.1663401096E+09 0.6000E+02 0.0 none O.OOOOE+(20 none O.OOOOE+(20 none O.OOOOE+t20 Nuclide 003:

Kr-85 1

0.3382974720E+09 0.8500E+02 8.551E+02 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 004:

Kr-85m 1

0.1612800000E+05 0.8500E+02 5.880E+03 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005:

Kr-87 1

0.4578000000E+04 0.8700E+02 1.175e+04 Rb-87 O.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006:

Kr-88 1

0.1022400000E+05 0.8800E+02

PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by John N.Hamawi Document ID32-5052589-01 Page 117 ARE VA 1.662E+04 Rb-88 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07

-0.8900E+02 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 0.0 Y-90 O.1OOOE+ 01 none O.OOOOE+ -00 DO none O.OOOOE+I Nuclide 010:

Sr-91 5

DO 0.3420000000E+05 00 0.9100E+02 0.0 Y-9lm 0.5800E+1 Y-91 0.4200E+I DO none O.OOOOE+1 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 0.0 Y-92 0.1000E+t)0 none O.OOOOE+(00 none O.OOOOE+(00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 0.0

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 118 AR EVA none 0.0000E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 0.0 Zr-93 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 0.0 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none. O.OOOOE+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 0.0 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none O.OOOOE+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 0.0 none 0.OOOOE+00 none O.OOOOE+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 119 AR EVA none O.OOOOE+OO Nuclide 019:

Mo-99 7

0.2376000000E+06 O.9900E+02 0.0 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none O.OOOOE+0O Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 0.0 Tc-99 0.1000E+O1 none O.OOOOE+00 none O.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 0.0 Rh-103m 0.100OE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 0.0 Rh-105 0.1000E+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 0.0 Rh-106 0.1000E+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 0.0 none O.OOOOE+00 none O.OOOOE+O0 none O.OOOOE+00 Nuclide 025:

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 120 AR EVA Sb-127 4

0.3326400000E+06 0.1270E+03 0.0 Te-127m 0.1800E+O0 Te-127 0.8200E+O0 none O.OOOOE+O0 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 0.0 Te-129m 0.2200E+00 Te-129 0.7700E+00 none O.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 0.0 none O.OOOOE+00 none 0.OOOOE+OO none O.OOOOE+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.127OE+03 0.0 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 0.0 1-129 0.1000E+ 01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 0.0 Te-129 0.6500E+00 1-129 0.3500E+00 none O.OOOOE+00 Nuclide 031:

Te-131m 4

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Document ID32-5052589-01 Page 121 AR EVA 0.1080000000E+06 0.1310E+03 0.0 Te-131 0.2200E+00 I-131 0.7800E+00 none 0.OOOOE+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 0.0 1-132 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03 2.717E+04 Xe-131m 0.11OOE-01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 034:

1-132 2

0.8280000000E+04 0.1320E+03 2.411e+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 035:

1-133 2

0.7488000000E+05 0.1330E+03 3.417E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 Nuclide 036:

1-134 2

0.3156000000E+04 0.1340E+03 3.815E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03

Document ID32-5052589-01 A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 122 AR EVA 3.182E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+OO Nuclide 038:

Xe-133 1

0.4531680000E+06 0.133OE+03 3.417E+04 none O.OOOOE+00 none O.OOOOE+O0 none O.OOOOE+OO Nuclide 039:

Xe-135 1

0.3272400000E+05 0.135OE+03 1.744E+04-Cs-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 040:

Cs-134 3

0.6507177120E+08 0.1340E+03 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041:

Cs-136 3

0.1131840000E+07 0.1360E+03 0.0 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+0O Nuclide 042:

Cs-137 3

0.9467280000E+09 0.1370E+03 0.0 Ba-137m 0.9500E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043:

Ba-139 6

0.4962000000E+04 0.1390E+03 0.0

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by John N.Hamawi Document ID32-5052589-01 Page 123 AR EVA none O.OOO0E+00 none O.0OOOE+OO none 0.OOOOE+OO Nuclide 044:

Ba-140 6

0.11007 736000E+07 0.1400E:+03 0.0 La-140 O.lOOOE+O1 none O.OOOOE+00 none O.OOOOE+00 Nuclide 045:

La-140 9

0.1449792000E+06 0.1400E+03 0.0 none O.0OOOE+1DO none O.OOOOE+100 none O.OOOOE+100 Nuclide 046:

La-141 9

0.1414800000E+05 0.1410E+03 0.0 Ce-141 O.10OOE+1D0 none O.OOOOE+1DO none O.OOOOE+1DO Nuclide 047:

La-142 9

0.5550000000E+04 0.1420E+03 0.0 none O.OOOOE+1DO none O.OOOOE+120 none O.OOOOE+1DO Nuclide 048:

Ce-141 8

0.2808086400E+07 0.1410E+03 0.0 none O.0OOOE+OO none O.OOOOE+00 none O.OOOOE+00 Nuclide 049:

Ce-143 8

0.1188000000E+06 0.1430E+03 0.0 Pr-143 O.1OOOE+01 none O.OOOOE+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32*505258901 Page 124 AR EVA none O.OOOOE+OO Nuclide 050:

Ce-144 8

0.2456352000E+08 0.1440E+03 0.0 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none O.OOOOE+00 Nuclide 051:

Pr-143 9

0.1171584000E+07 0.143OE+03 0.0 none O.OOOOE+00 none O.OOOOE+00 none -0.0000E+0O Nuclide 052:

Nd-147 9

0.9486720000E+06 0.147OE+03 0.0 Pm-147 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:

Np-239 8

0.2034i720000E+06 0.23901E+03 0.0 Pu-239 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 054:

Pu-238 8

0.2768fB63824E+10 0.23801E+03 0.0 U-234 0.1000E+01 none O.OOOOE+00 none O.OOOOE+O0 Nuclide 055:

Pu-239 8

0.75943336440E+12 0.23901E+03 0.0 U-235 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 056:

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 125 AR EVA Pu-240 8

0.2062920312E+12 0.2400E+03 0.0 U-236 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 057:

Pu-241 8

0.4544294400E+09 0.2410E+03 0.0 U-237 0.2400E-04 Am-241 0.1000E+01 none O.OOOOE+00 Nuclide 058:

Am-2441 9

0.1363919472E+ll 0.2410E+03 0.0 Np-237 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 059:

Cm-242 9

0.1406592000E+08 0.2420E+03 0.0 Pu-238 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 060:

Cm-244 9

0.5715081360E+09 0.2440E+03 0.0 Pu-240 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 End of Nuclear Inventory File

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 126 AR EVA RADTRAD Run Case #A - Release Fraction and Timing File Release Fraction and Timing RG 1.183, Appendix B with pool DF = 200 for halogens Duration (h): NON-LOCA Accident chk inventory 1.OOOOE-03 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Noble Gases:

1.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Iodine:

5.OOOE-03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Cesium:

0.0000E+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Tellurium:

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

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

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

O.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Cerium:

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

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

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 End of Release File

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 127 AR EVA RADTRAD Run Case #A - Main Output File

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 128 A R EVA RADTRAD Version 3.03 (Spring 2001) run on 11/02/2004 at 15:33:14 File information Plant file = C:\calcs\calcs-PNPS\AST\AST-FHA\PNPS-RADTRAD-FHA.psf Inventory file = c:\calcs\calcs-pnps\ast\ast-fha\pnps-radtrad-fha.nif Release file = c:\calcs\calcs-pnps\ast\ast-fha\non_loca.rft Dose Conversion file = c:\software\radtrad\defaults\fgrll&12.inp

- - - *###41 t * * ## # * #

# * ##

it

* * #* it

1. 1. 1. # it Radtrad 3.03 4/15/2001 FHA: NO SGTS, NO CRHEAFS - 24 hrs Decay Nuclide Inventory File:

c:\calcs\calcs-pnps\ast\ast-fha\pnps-radtrad-fha.nif Plant Power Level:

1.2110E+01 Compartments:

3 Compartment 1:

Refuel Floor 3

7.OOOOE+O5 0

0 0

Compartment 2:

Atmosphere 2

O.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 129 AR EVA 3.4280E+04 0

0 0

Pathways:

3 Pathway 1:

FHA Release via RB Vent 1

2 4

Pathway 2:

CR intake 2

3 2

Pathway 3:

CR exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OOOOE+OO c:\software\radtrad\defaults\fgrll&12.inp c:\calcs\calcs-pnps\ast\ast-fha\non_loca.rft 2.4000E+0l 1

O.OOOOE+00 5.7000E-01 4.3000E-01 l.OOOOE+00 Overlying Pool:

0 O.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N. Hamawi Document ID32-5052589-01 Page 130 AR EVA 0

1 0

0 0

Compartment 3:

0 1

0 0

Pathways:

3 Pathway 1:'

0 0

1 2

2 .4000 E+01 9.6000E+03 2.6000E+01 O.OOOOE+00 0

Pathway 2:

0 0

0 1

2 2 .4000E+01 9.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7 .4400E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 3:

0 0

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 131 AREVA 0

0 0

1 2

2.4000E+01 9.OOOOE+03 O.OOOOE+OO 0.OOOOE+00 O.OOOOE+00 7.4400E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 2

1 2

2.4000E+01 7.4790E-04 2.6000E+01 O.OOOOE+00 1

4 2.4000E+O1 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 O.OOOOE+O0 0

Location 2:

LPZ 2

1 2

2.4000E+01 3.6920E-05 2.6000E+01 O.OOOOE+00 1

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

Location 3:

CR 3

0 1

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

4 2.4000E+01 1.OOOOE+OO 4.8000E+01 6.OOOOE-O1 1.2000E+02 4 .OOOOE-01

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 132 AR EVA 7.4400E+02 O.OOOOE+00 Effective Volume Location:

1 2

2.4000E+01 1.7600E-03 2.6000E+01 O.OOOOE+00 Simulation Parameters:

1 2.4000E401 O.OOOOE+00 Output Filename:

C:\calcs\calcs-PNPS\AST\AST-FHA\PNPS-RADTRAD-FHA.o2 1

1 1

0 0

End of Scenario File

.A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by-. John N.Hamawi Document ID32-5052589-01 Page 133 AR EVA RADTRAD Version 3.03 (Spring 2001) run on 11/02/2004 at 15:33:14 Plant Description Number of Nuclides = 60 Inventory Power = 1.2110E+01 MWth Plant Power Level = 1.2110E+01 MWth Number of compartments = 3 Compartment information Compartment number- 1 (Source term fraction = l.COOOE+00

)

Name: Refuel Floor Compartment volume = 7.OOOOE+05 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: FHA Release via RB Vent Compartment number 2 Name: Atmosphere Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: FEA Release via RB Vent Inlet Pathway Number 3: CR exhaust Exit Pathway Number 2: CR intake Compartment number 3 Name: Control Room Compartment volume = 3.4280E+04 (Cubic feet)

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

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Document ID32-5052589-01 Page 134 AR EVA RADTRAD Version 3.03 (Spring 2001) run on 11/02/2004 at 15:33:14 Scenario Description Time between shutdown and first release = 2.4000E+01 (Hours)

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.001000 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.0000E+00 O.OO0OE+oo O. OOOOE+00 2.-371E+00 IODINE 5.0000E-03 0.0000E+00 0.0000E+00 1.311E-03 CESIUM 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.000E+00 TELLURIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+00 O.OOOE+00 STRONTIUM 0.0000E+00 o.OOOOE+00 0.OOOOE+00 0.000E+00 BARIUM 0.0000E+00 o.OOOOE+00 0.OOOOE+00 o.OOOE+00 RUTHENIUM 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOE+00 CERIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM o.OOOOE+00 0.OOOOE+00 0.0000E+00 0.000E+00 Inventory Power = 1. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-85 1 8.551E+02 3.383E+08 1.190E-16 0.OOOE+00 0.OOOE+00 Kr-85m 1 5.880E+03 1.613E+04 7.480E-15 0.000E+00 0.OOOE+O0 Kr-87 1 1.175E+04 4.578E+03 4.120E-14 0.OOOE+00 0.OOOE+00 Kr-88 1 1.662E+04 1.022E+04 1.020E-13 0.OOOE+00 0.OOOE+00 I-131 2 2.717E+04 6.947E+05 1.820E-14 2.920E-07 8.890E-09 1-132 2 2.411E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 3.417E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 3.815E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 1-135 2 3.182E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 3.417E+04 4.532E+05 1.560E-15 0.OOOE+00 0.000E+00 Xe-135 1 1.744E+04 3.272E+04 1.190E-14 0.OOOE+00 0.OOOE+00 Nuclide Daughter Fraction Daughter Fractiorn Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00 1-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Iodine fractions Aerosol - 0.0000E+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 135 AR EVA Elemental = 5.7000E-01 Organic = 4.3000E-01 COMPARTMENT DATA Compartment number 1: Refuel Floor Compartment number 2: Atmosphere Compartment number 3: Control Room PATHWAY DATA Pathway number 1: FHA Release via RB Vent Convection Data Time (hr) Flow Rate (% / day) 2.4000E+01 9.6000E+03 2.6000E+01 0.OOOOE+CO Pathway number 2: CR intake Pathway Filter: Removal Data Time (hr) Flow Rate Filte3: Efficiencies s(%)

(cfm) Aerosol Elemental Organic 2.4000E+O1 9.OOOOE+03 o.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.4400E+02 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 3: CR exhaust Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 9.OOOOE+03 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.4400E+02 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location EAB is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m'^-3) 2.4000E+01 7.4790E-04 2.6000E+01 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3

sec^-l) 2.4000E+01 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 0.OOOOE+00 Location LPZ i.. in compartment 2 Location X/Q Data Time (hr) X/Q (S

MA -3)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 136 AR EVA 2.4000E+01 3.6920E-05 2.6000E+O1 O.OOOOE+00 Location Breathi.ng Rate Data Time (hr) Breathing Rate (m^3

secA-1) 2.4000E+O1 3.5000E-04 3.2000E+01 1.80OOE-04 4.8000E+01 2.3000E-04 7.4400E+02 O.OOOOE+00 Location CR is in compartment 3 Location X/Q Dat Time (hr) X/Q (s

mA-3) 2.4000E+O1 1.7600E-03 2.6000E+01 O.OOOOE+00 Location Breathi.ng Rate Data Time (hr) Breathing Rate (mA3

secA-1) 2.4000E+01 3.5000E-04 7.4400E+02 O.OOOOE+00 Location Occuparicy Factor Data Time (hr) Occupancy Factor 2.4000E+01 1.OOOOE+00 4.8000E+0l 6.OOOOE-O1 1.2000E+02 4-.0000E-01 7.4400E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+OO O.OOOOE+OO

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 137 AR EVA

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Dose Output 4AB4#44Doses: 4*####4444*4 #444#4 ## ##4*###

EAB Doses:

Time (h) = 24.0010 Whole Body Thyroid TEDE Delta dose (rem) 9.0948E-04 7.7828E-02 3.2957E-03 Accumulated dose (rem) 9.0948E-04 7.7828E-02 3.2957E-03 LPZ Doses:

Time (h) = 24.0010 Whole Body Thyroid TEDE Delta dose (rem) 4.4896E-05 3.8420E-03 1.6269E-04 Accumulated dose (rem) 4.4896E-05 3.8420E-03 1.6269E-04 CR Doses:

Time (h) = 24.0010 Whole Body Thyroid TEDE Delta dose (rem) 3.6762E-07 1.0820E-03 3.3541E-05 Accumulated dose (rem) 3.6762E-07 1.0820E-03 3.3541E-05 EAB Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.4903E-01 3.8823E+01 1.6393E+00 Accumulated dose (rem) 4.4994E-0l 3.8901E+01 1.6426E+00 LPZ Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2166E-02 1.9165E+00 8.0924E-02 Accumulated dose (rem) 2.2211E-02 1.9203E+00 8.1087E-02 CR Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9136E-02 8.6972E+0l 2.6956E+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamawi Document ID32-5052589-01 Page 138 AREVA Accumulated dose (rem) 2.9137E-02 8.6974E+0l 2.6956E+00 EAB Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 Accumulated dose (rem) 4.4994E-01 3.8901E+01 1.6426E+00 LPZ Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.2211E-02 1.9203E+00 8.1087E-02 CR Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.8136E-06 1.2410E-02 3.8413E-04 Accumulated dose (rem) - :2.9140E 8:6986E+01 .2.6960E+00 EAB Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.4994E-0l 3.8901E+01 1. 6426E+00 LPZ Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.2211E-02 1.9203E+00 8.1087E-02 CR Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5484E-47 1.0706E-43 3.3026E-45 Accumulated dose (rem) 2.9140E-02 8.6986E+01 2.6960E+00 EAB Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.4994E-01 3.8901E+01 1.6426E+00 LPZ Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 2.2211E-02 1.9203E+00 8.1087E-02 CR Doses:

Time (h) = 120.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0254-156 1.3267-152 4.0729-154 Accumulated dose (rem) 2.9140E-02 8.6986E+01 2.6960E+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Altemative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 139 AR EVA EAB Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.4994E-01 3.8901E+01 1.6426E+00 LPZ Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose {rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.2211E-02 1.9203E+00 8.1087E-02 CR Doses:

Time (h) = 744.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.9140E-02 8.6986E+01 2.6960E+00 837 I-131 Summary Refuel Floor Atmosphere Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 24.000 6.9161E+01 7.6874E-02 5.7301E-04 24.001 1.2438E+02 2.4892E-01 1.8511E-03

24. 401 2.5076E+01 9.9444E+01 6.3225E-02 24.701 7.5445E+00 1.1696E+02 1.9191E-02 25.001 2.2699E+00 1.2223E+02 5.7754E-03 25.301 6.8295E-01 1.2381E+02 1.7377E-03 25.601 2.0548E-01 1.2429E+02 5.2281E-04 25.901 6.1822E-02 1.2443E+02 1.5730E-04 26.000 4.1592E-02 1.2445E+02 1.0582E-04 26.300 4.1547E-02 1.2445E+02 9.3694E-07 26.600 4.1503E-02 1.2445E+02 8.2955E-09 26.900 4.1458E-02 1.2445E+02 7.3447E-11 27.200 4.1413E-02 1.2445E+02 6.5028E-13 27.500 4.1369E-02 1.2445E+02 5.7575E-15 27.800 4.1324E-02 1.2445E+02 5.0975E-17 28.100 4.1280E-02 1.2445E+02 4.5132E-19 28.400 4.1235E-02 1.2445E+02 3.9959E-21 28.700 4.1191E-02 1.2445E+02 3.5379E-23 29.000 4.1146E-02 1.2445E+02 3.1324E-25 29.3 00 4.1102E-02 1.2445E+02 2.7734E-27 29.600 4.105SE-02 1.2445E+02 2.4555E-29 29.900 4.1013E-02 1.2445E+02 2.1740E-31 30.200 4.0969E-02 1.2445E+02 1.9248E-33 30.500 4.0925E-02 1 .2445E+02 1.7042E-35 30.800 4.0881E-02 1.2445E+02 1.5089E-37 31.100 4.0837E-02 1.2445E+02 1.3359E-39 31.4 00 4.0793E-02 1.2445E+02 1.1828E-41 31.700 4.0749E-02 1.2445E+02 1.0472E-43 32.000 4.0705E-02 1.2445E+02 9.2719E-46 32.300 4.0661E-02 1.2445E+02 8.2091E-48

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N.Hamnawi Document ID32-5052589-01 Page 140 AR EVA 32.600 4.0618E-02 1.2445E+02 7.2682E-50 32.900 4.0574E-02 1.2445E+02 6.4351E-52 33.200 4.0530E-02 1.2445E+02 5.6975E-54 33.500 4.0487E-02 1.2445E+02 5.0445E-56 33.800 4.0443E-02 1.2445E+02 4.4662E-58 34.100 4.0399E-02 1.2445E+02 3.9543E-60 34.400 4.0356E-02 1.2445E+02 3.5011E-62

48. 000 3.8432E-02 1.2445E+02 3.0019-155 120. 000 2.9673E-02 1.2445E+02 O.OOOOE+00 744. 000 3.1542E-03 1. 2445E+02 O.OOOOE+00 Cumulative Dose Summary EAB LPZ CR Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 24.000 0.0000E+00 O.OOOOE+00 *O.00E+00 O.000E+00 0.0000E+00 O.OOOOE+00 24.001 7.7828E-02 3.2957E-03 3.8420E-03 1.6269E-04 1.0820E-03 3.3541E-05 24.401 3.1093E+01 1.3148E+00 1.5349E+00 6.4904E-02 6.2088E+01 1.9245E+00 24.701 3.6563E+01 1.5448E+00 1.8049E+00 7.6260E-02 7.9502E+01 2.4642E+00 25.001 3.8207E+01 1.6137E+00 1.8861E+00 7.9660E-02 8.4756E+01 2.6269E+00 25.301 3.8701E+01 1.6343E+00 1.9105E+00 8.0678E-02 8.6336E+01 2.6759E+00 25.601 3.8850E+01 1.6405E+00 1.9178E+00 8.0983E-02 8.6811E+01 2.6906E+00 25.901 3.8894E+01 1.6423E+00 1.9200E+00 8.1074E-02 8.6953E+01 2.6950E+00 26.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6974E+01 2.6956E+00 26.300 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 26.600 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 26.900 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 27.200 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 27.500 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 27.800 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 28.100 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 28.400 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 28.700 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 29.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 29.300 3.8901E+01 1. 6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 29.600 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 29.900 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 30.200 3.8901E+01 1. 6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 30.500 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 30.800 3.8901E+0l 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 31.100 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 31.400 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 31.700 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 32.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 32.300 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 32.600 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 32.900 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 33.200 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 33.500 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 33.800 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 34.100 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 34.400 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 48.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N.Hamawi Document ID32-5052589-01 Page 141 AR EVA 8.6986E+O1 2.6960E+O0 120.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 120.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 744.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+01 2.6960E+00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) *(rem) 24.0 4.4994E-01 3.8901E+01 1.6426E+00

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