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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	32-5052589-01
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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, "Radiological Consequences of a Design-Basis Fuel Handling Accident Based on the Alternate Source Term Methodology', (141 pages)

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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 in the 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). It is concluded that the CR TEDE dose documented in this 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 Is safety-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 in the 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 Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

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, in all pages.

(2)

Moved the 'Record of Revisions' from page 4 lo 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 is for 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 in the 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 (1 996-2000) 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, in Table 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) is initiated 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) 1 of 2 ADESIGN VERIFICATION CHECKLIST I AREVA 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 O N 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 0

Y 0 N 16 NIA appropriately specified?

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?

Frarna tome 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(

fggud egg r

/y A~ (tsS j19t/lho.

uednc, e Verified By:

Jo-Ann Pelczar

.4/4/L (First, MI, Last)

Printed / Typed Name Signature Date Framatome ANP, Inm, an AREVA and Siemens company \\,_/

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Alternative Source Term Methodology (2038 MWt)

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 a Glance.29 D.

Copies of Selected References.31 E

Uist of Computer Runs.................................

38-14 1

A AR EVA 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 ID 32-5052589-01 Page 6

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 is bounding for the following core parameters:

Power level:

Fuel enrichment:

Core loading:

Bumup:

c 2038 MWt 3.9 - 4.6 w/o U-235 101.8 - 105.56 MTU (metric tons of uranium) 5 -60 GWDIMTU For each radionuclide, the core inventory corresponds to the bounding value within the listed ranges of enrichment, core loading, and burnup. In general, 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:

High 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 1-131,1-132 Kr-85 Xe-131m, Xe-133m, Xe-135m With respect to enrichment, the grouping is as follows:

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

High enrichment: Kryptons, and Xe135

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Mcident Document ID 32-5052589-01 A

Based on the Alternative Source Term Methodology (2038 MWt)

ARE VA Prepared by: John N. Hamawi Page 7 The corresponding inventory in the 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 in the core. This adjustment factor is equal 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 is very 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 is also 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 in Attachment A for informational purposes.

A brief description of ELISA-2 is presented in Attachment C. It is noted 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 in the ELISA-2 outputs in Attachment 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 a Design-Basis Fuel Handling Accident Document ID 32.5052589-01 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 in the 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 is any assumption or limitation that must be verified prior to using the results and/or conclusions of a calculation for a safety-related task. There are no key assumptions in the 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 ID 32-5052589-01 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 in this analysis since there is no 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 a further 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 in the pre-cast panels from the refuel floor elevation 11'r-o to the top of the panels at elevation 165'-11 -.

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 ID 32-5052589-01 Page 10 (i)

Release to the atmosphere is within 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 is assumed 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 is an 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 is presented in Table 2.1.

Table 2.1 Pilgrim Station - Fuel Handling Accident Dose Results

[From Table 4.2]

- AST Methodology 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 is for 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 is 2.86 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 in Table 2.1 are bounding for the following core parameters:

Power level:

Fuel enrichment:

Core loading:

Bumup:

2038 MWt 3.9 -4.6 w/o U-235 101.8 - 105.56 MTU (metric tons of uranium) 5 -60 GWD/MTU

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Alternative Source Term Methodology (2038 MWI)

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 is less because the gamma (X/Q)s and the concentrations (XIQ)s at the LPZ are numerically close (in view 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)

In general, the CR FHA dose increases with increasing fresh air flow, but soon reaches a maximum value. A high flow rate leads to an increase in the amount of radioactivity which enters the control room, but also leads to an increase in the rate at which the contaminated air is exhausted from the control room. Thus, the airborne concentration in the 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. In the present applicaton, the difference in the CR dose between a fresh 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 is to 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 in the ELISA-2 computer outputs in Attachment E of this calculation.

(g)

In line 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 in case of a fuel handling accident during refueling operations.

(h)

Based on the conclusion discussed under Item (e) above, the CR TEDE dose documented in this calculation is bounding 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 a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 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 in the analysis, and the associated references, are summarized in Tables 3.1 through 3.3. The majority of the information in Table 3.1 was extracted from Ref. 12; a copy of this reference appears in Attachment D.

Pertinent assumptions employed in the 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 in the reactor cavity. A fuel assembly dropped in the spent fuel pool would result in fewer 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 in Table 3.1 (Item #A6) is for 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 is the 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). 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-tightness (see Footnote 2 in Sec. 2).

(e)

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

(f)

In line 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 a 2-hour interval. Analytically, this was accomplished by assuming a building air exchange rate of 4 air 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 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).

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 ID 32-5052589-01 Page 13 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 (1 0xl0 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, in peak-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 AREVA 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 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)

B to 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 is approximately at El. 70 fi; the water level during refueling is at El. 116 ft. A fuel assembly dropped in the spent fuel pool would result in fewer fuel rods damaged due to the significantly smaller drop height (Ref. 12). The water depth in the spent fuel pool is also> 23 ft [see Attachment D, Table Note (b)J.

(c)

Item #B6: Recent improvements to the building leak -tightness minimize RB siding leakage as a potential release pathway (Ref. 12). See Footnote 4 in Sec. 2. In addition, releases via the main stack are feasible if the Standby Gas Treatment System (SGTS) is initiated 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 (a low value), and 9000 cfm (a high value bounding the 7200 cfm listed in Ref. 12). The intent is to show that there is little impact on the CR dose for any flow within this range.

A AREVA 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 15 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 TEDE 5 rem Ref. 1, pg 1.183-19, and Contol rom TDE 5rem Ref. 16, Sec. (b)(2)(iiii)

DSRegulatory dose limits EAB TEDE 6.3 rem Ref. 1, Table 6 LPZ TEDE 6.3 rem (e)

Item #D4: Even though all radioactivity is released 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 AR 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 ID 32-5052589-01 Page 16 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:

Fuel enrichment:

Core loading:

Bumup:

2038 MWt 3.9 - 4.6 w/. U-235 101.8 - 105.56 MTU (metric tons of uranium) 5 -60 GWD/MTU (b)

The maximum bumup at the end of Cycle 15 is predicted to be 51.7 GWD/MTU [19). Therefore, the condition of Footnote 11 of Reg. Guide 1.183 (Ref. 1, page 1.183-14] is met and the fractions given in Regulatory Guide 1.183, Table 3, apply.

A AREVA 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 17 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. (X/Q)

Gamma (XIQP)

_(sec/m

3)

_ _ (sec/rn 3) 1 EAB (actual) Ca) 0 - 2 hrs 7.479E-04 3.199E-04 0 - 2 hrs 3.692E-05 3.551 E-05 2 - 8 hrs 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 in the atmospheric dispersion analysis are from the closest point of the reactor building; as such, they conservatively apply to releases via the RB vent, which is at the plant SW comer. The critical receptor is in the true NE sector, at a distance of 486 m (at the over-water exclusion zone).

(b) See Attachment A for definition of the gamma ( IQ). The gamma (Q/Q) is energy 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 is in 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 ID 32-5052589-01 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 9 for the decay-corrected activity.

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. Harnawi Document ID 32-5052589-01 Page 19 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 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 ID 32-5052589-01 Page 20 4.3 Results The design input in Sec. 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 in Table 4.2.

The following are noted:

(a)

The thyroid and skin doses presented in this 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 E for 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 AR EVA 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 ID 32-5052589-01 Page 21 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)

Reference 28691.32 2.059 Case #A, Control 1000 cfm 2.846 0.0455

[99.95

[97.25]

26se

A 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.

N/A 0.0920 0.0330 1.954 0.0836 Case LPZ

'30 days NA

[64.12]

[.33 98.33]

[52.54]

17pu P

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. A sample 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.

PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Altemative Source Term Methodology (2038 MWt)

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-3 -A Computer 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)

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Altemative Source Term Methodology (2038 MW1)

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 in Air, 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 in October 2004.)

20.

J. V. Ramsdell and C. A. Simonen, 'Atmospheric Relative Concentrations in Building 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 in the 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 A for a copy of this reference, or excerpts thereof.

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the AHemative Source Term Methodology (2038 MWI)

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 is provided 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.

In the 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 AREVA 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 ID 32-5052589-01 Page 25 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)

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 PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Alternative Source Term Methodology (2038 MWI)

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

As pointed out in the 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 in finite clouds of radioactive material.

The manner in which these parameters are applied in the assessment of offsite radiological impacts is presented below for additional clarification.

By definition, the (XIQ)c is a 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. If consideration 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 PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Altemative Source Term Methodology (2038 MWI)

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 (a simplistic 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-m3lhr-buci),

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

It could 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 is assumed 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].

In the 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 in the 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 in detail 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 in the above equations represent either plume centerline

A AR 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 ID 32-5052589-01 Page 28 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:

and (XIQ)g

= 2 Pa (h1 + K 12) I(ITu)

(XIQ)g

= 2 Pa (11 + K 12) / [X U (T/8)]

(plume centerline model)

(sector-average model)

(5)

(6)

In these equations:

p

=

linear attenuation coefficient for air at a given gamma energy (1r/m),

Pa

=

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

K U

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

K = (P - Pa) / la,

=

prevailing wind speed (m/sec),

=

downwind distance (m), and (Tr/8)

=

angular width of a 22.5-degree sector.

Parameters Ix, (2, 11 and 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 PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 A

Based on the Alternative Source Term Methodology (2038 MWI)

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 in the core and in any 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.

PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by. John N. Hamawi 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 AREVA 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 ATTACHMENT D COPIES OF SELECTED REFERENCES Included in this attachment is a 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 AREVA 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 ID 32-5052589-01 Page 32 Reference 12 E

y 75 IEntergy Nudear Generation Company E n t y

Pilgrym Nuclear Power S0a26 on TV GOO Rocky Kilt Rosad Plymou~th. MA 02360 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 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 ID 32-5052589-01 Page 33 Entergy 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 in core 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 1 Oxl0 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)

b 23 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. 1 B and 10 species), for main slack releases Rebuerng bvel leak tightness has been recently improved. Maintenance Request MRD4 107653 was implemenled hI October 204 lo reseal the Joints In ve reactor bulkding pre-cast panels. ThIs MRwas compeited under Nuclear Change ER03121X)S8 Reseal Joints In Pre-Cast Panels.

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

.~..:iet sep oi he pan s atelevation 165-

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

A AR 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 ID 32-5052589-01 Page 34 E-ntergy 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 EL 37. 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 so 9900 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 as plus 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 C7(c) Control room charcoal filtration iodine removal efficiency 95%

R IC C7"' (all species) 95 %_Ref._1_C 001 1I

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-1 ABased on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by: John N. Hamawi Page 35 Entegy 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 in the 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 1 16-78.25-14.39-23.36 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 Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

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 AR EVA 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 ID 32-5052589-01 Page 37

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

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 ABased on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by: John N. Hamawi Page 38 ATTACHMENTE LIST OF COMPUTER RUNS Included in this 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 is noted that both ELISA-2 and RADTRAD main output files include the listings of the input files.

A AREVA 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 ID 32-5052589-01 Page 39 ELISA-2 Run Case #A - Main Output File

A AR EVA PNPS-Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Tern Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 40 4##t### #

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1 May 23,2002 PROBLEM SUBMITTED ON.. :

28-Oct-04 1745s:33 INPUT FILE............

1 DATA LIBRARY FILE.....

1 OUTPUT FILE...........

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A AR 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 ID 32-5052589-01 Page 41 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 Seq.

1 2

3 4

5 6

7 8

9 10 11 12 123456789012345678901234567890123456789012345679901234567890123456789012345678901234567890123456789012345678901234567890 1

PNPS AST -

2 10002 3

10003 4

10004 3

S 1

6 2

7 3

8 10006 9

BR82 10 BR84M 11 BROS 12 1128 13 1131 14 1134M 15 1183 16 XR88 17 XE131M 18 XZ135M 19 10007 20 10009 21 10010 4

22 0.0

-4 23 10018 24 0.0 25 10021 26 0.0 27 10024 28 0.0 29 99999

FA BOUNDING SRC 4

6 a

O 1.0 24.0 24 HR DZCAY -

RB VENT RELEASES -

CR -

1000 CFM 1

0 NNYNNY N NNN YYYYYY 0.0 0.0 0

1.0003+00 2.8503-03

.0000+00 1.OOOZ+OO 2.042B+02 1.328B+02 1.130Z+04 5.702B+02 2.7173+04

.074B+03 2.567B+03 1.6621+04 1.905E+02 5.8253+03 2 7.03+05 2 34280.0 0

.000X+00

.000+00 2.150E-03

.000e+00

.000oz00

.0003+00

.000o+00 DR82M 7.892E+01 BR83 BR85 5.8158+03 8R86 KR X8 BR I ZZ 2.567B+03 BR84 4.356B+03 BR87 1129 1132 1135 KR85 XR89 XE133 XZ137 96.0 1000.0 1.793R-03 2.4113+04 3.1821+04 8.551.+02 22.096Z+04 3.4173+04 3.0073+04 0.0 0.0 1130 1133 1136 3S85K SR90 X3133K X1138 0.0 0.0 1.3833+03 3.4171+04 1.544E+04 5.880+03 2.081Z+04 1.0523+03 3.037E+04 0.0 0.0 I130M 1134 1136M 1R87 4.7333+03 9.921Z+03 5.402X102 3.8151+04 9.4461+03 1.175S+04 X8135 XE139 0.0 0.0 1.744Z+04 2.4471+04

'Refueling Level,

'Control Room' I

0.5 1.0 720.0 5

1.7603-03 2.0 1.2501-03 8.0 4.2603-04 24.0 3.6701-04 96.0 3.1501-04 L

3.5Z-04 3

1.0 24.0 0.6 96.0 0.4 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

35 2

36 3

37 10006 38 bR82 39 BR84M 40 BR88 41 1128 42 1131 43 1134M 1.0000Z+0

.OOO+.00

.OOO+00 2.850B-03 2.150Z-03

.0001+00 0.000+00

.00O0Z00

.0001.00

-1.000B+00

.000X+00 2.0423+02 BR82M 7.992Z+01 BR83 1.3288+02 BROS 5.815B+03 BR86 1.130X.04 5.702B+02 1129 1.7938-03 1130 2.7178+04 1132 2.411E+04 1133 4.074Z+03 X135 3.182Z+04 1136 3R XB BR I zz 2.5671+03 BR84 4.356E+03 BR87 1.3833+03 I130M 3.417E+04 r134 1.5448+04 X136M 4.7333.03

9. 9213+03

5. 4023+02 3.8153+04

9. 446E+03

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 ID 32-5052589-01 Page 42 44 1R835 45 FR88 46 X3131M 47 X3135M 48 10007 2.5675+03 XR85 1.662Z+04 XR89 1.9053+02 Xe133 6.8255+03 X3137 2 7.0X+05 96.0 8.5513+02 5RO5H 2.096X+04 XR90 3.4175+04 X51335 3.0075+04 XZ138 0.0 0.0 5.8805.03 5R87 2.0813+04 1.0525E03 X3135 3.0373+04 X3139 0.0 0.0 1.1755+04 1*7443+04 2.447E+04

'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 Seq.

1 2

3 4

5 6

7 8

9 10 11 12 123456789012345678901234567890123456789012345678901234567890123456789012345678901234567090123456789012345678901234567890 49 10009 50 10010 51 0.0 52 10018 53 0.0 54 10021 55 0.0 56 10024 57 0.0 58 99999 2 34280.0 9000.0 4

0.0 0.0 0.0 0.0

'Control Rooc' 0.5 1.0 720.0 5

1.7603-03 2.0 1.2505-03 8.0 4.260z-04 24.0 3.6705-04 96.0 3.150B-04 1

3.5B-04 3

1.0 24.0 0.6 96.0 0.4

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

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 AREVA 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 44 44 45 46

7 48 3.0003-01 2.500E+00 3

Factors to 1.0 1.0 4.500-018 7.0003-01 1.OOOZ+OO 1.5003.00 2.0003+00 3.000+00 4.0003+00 6.0005+00 8.000E+00 1.1003+01 convert data library DCFe to proper units, an shown Convert air inmmrsion DCX to (((Sv or Gy)/u)/(Bq/m3)]

Convert ground nhino DCx to 1((By or or)/&)/(Bq/m2)3 V2L1 V2L1 V2LI V2LI V2L1 41 42 43 44 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 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 1.0 Convert inhalation DC? to Isy/Bq]

18 Air ga-a DCF for semi-infinite monoener. cloud arc [((y/s)/(Bq/m3)]

6.676Z-16 1.669E-15 2.503Z-15 3.839B-15 5.674Z-15 8.345Z-15 1.5023-14 2.5033-14 3.839Z-14 5.6741-14 8.345E-14 1.1683-13 1.5023-13 1.836Z-13 2.337Z-13 3.3383-13 4.6733-13 6.3423-13 18 Air ga=m DCx for monoenerg. ground-surface source C(ay/s)/ (q/12)]

1.8293-16 1.4933-16 9.8353-17 8.181Z-17 9.767Z-17 1.436E-16 2.760Z-16 4.7853-16 7.3185-16 1.050E-15 1.4573-15 1.9103-15 2.3253-15 2.710Z-15 3.2433-15 4.194E-15 5.386E-15 6.759E-15 18 Skin gaem DCZ for semi-infinite monoener. cloud *rc t(Sv/n)/(Bq/m3)3 1.138E-16 7.6903-16 1.467z-15 2.717E-15 4.416Z-15 6.737E-15 1.239B-14 2.0738-14 3.193E-14 4.7543-14 7.1083-14 1.0123-13 1.3173-13 1.6248-13 2.0893-13 3.030Z-13 4.305Z-13 5.922E-13 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2LI.

V2L1 MIL V2L1 RADIONUCLIDE DATA BASE I

R 3 (tre Ci) 1.4713+01 2.1863+01 1.744E+01 2.5363+01 Decay chain, decay constants and branching fraction.

3 6.403203-06

.00000+00.OOOOO+00

.0003+00

.0005+00 ORIGHN-2 18-group phot/die, and ICRP-38 betas (MoV/die)

.0005+00

.00OZ+00

.000+00

.000t00

.0003+OO

.000+00

.OOO+00

.OOOE400

.0003+00

.0005+00

.OOO00

.0003+00 5.600Z-03 72 ICRP-38 Organ DCFs - Air l4-er, Grnd shine, Inbal/Claee V 73

.0005+00

.000+.00 2.750E-18

.0005+00

.000E+00 74

.0003+00 3.310Z-19

.0003+00

.OOO+00

.OOOE300 75

.0003+00

.000z+00

.0005+00

.0003+00

.0005+00 76

.0005+00

.0003+00

.000Z+00

.00oz+00

.0003+00 77 1.730Z-11 1.730Z-11 1.7303-11 1.7303-11 1.730E-11 78 1.730Z-11 1.7303-11

.000.+00

.0003+00 79 2

C 14 (Src Ci) 3.125Z-06 4.723Z-06 3.772Z-06 5.467E-06 80 Decay chain, decay constants and branching fractions 81 C 14 82 1.38016Z-08

.000003+00

.0003+00

.0003+00 83 ORIGEN-2 18-group pbot/dis, and ICRP-38 beta. (MeV/dis) 84

.0003+00

.0008+00

.0003+00

.00O0+00 85

.0oooeoo

.0003+00

.000o.00

.0003+00

.OOO0oo 86

.000*+00

.0003+00

.000+.00

.0003.00 87 4.940E-02 V2L1 V2L1 V2L1 V2L1

.OOOE00 V2L1 V2L1

.0005+00 V2L1

.OOO+00 V2L1

.OOO+00 V2L1 V2L1 V2L1

.0003.00 V2L1 V2L1

.0003+00 V2L1 V2L1 L.730E-11 V2L1 V2L1 V2L1 V2L1 V2L1

.ooo0+oo V2L1 V2L1

.0003+00 V2L1

.000+.00 V2L1

.0003+00 V2L1 V2L1 46

'7 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 I

A ARE VA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by. John N. Hamawi Page 45 88 89 90 91 92 ICRP-38 Organ DCFr Air 2.590Z-19 3.5201-19 1.5401-19 2.2401-19 2.2201-20 2.520Z-20 1.030B-20 1.6101-20 immer, Grad shine, Tnhal/Clagg c 1.5301-19 1.210Z-19 7.0601-19

.0001+00

.000R+00 2.4301-16 8.650Z-21 7.2501-21 4.6301-20

.0001+00

.0001+00 7.4601-20 V2L1 2.190B-19 V2L1 V2L1 1.250Z-20 V2L1 V2L1 85 56 87 88 89 C.... etc., for a total of 414 radionuclides....,

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 A

Based on the Alternative Source Term Methodology (2038 MWt)

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 A

4 (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 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 ID 32.5052589-01 Page 47 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 2F1---------

1 O

2-----3O-O 2

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 2

.0000 3

.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 1

2 3

KR XZ BR r

zz

1. 000+.00 2.8501-03

.0001+00 FORM 2

.000+00 2.150B-03

.000x+00 FORM 3

.000x+00

.OOOE+00

.000z+00 ELEMENT 'ZZ" STANDS FOR THE REMAINING DATA-LIBRARY ELEMENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWI)

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 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 (hourn)

CONCZNTR.

X/Q (sec/=3)

CAMMA X/Q (sec/m3) 1.760E-03 1.760R-03 1.760B-03 1.250E-03 DEPOSITION D/Q (1/n2)

.00O1.00

. 000+00

. 000Z00

.000z+oo BREATHING RATE (m3/sec)

3. 500B-04 3.300E-04 3.5001-04 3.3001-04 eM. PILT.

BYPASS FRACTION

.0oooe00 0ooo+oo

.000E+00

. 0001+00 COMPART.

C INT.FrILTER BYPASS FR.

.OOOE094

.OOO+00

.ooo+00

. 00O0+00 COMPART. C OCCUPANCY FACTOR 1.0001+00 1.0001+00

1. 000.00 1.0001.00

.00001+00 5.0000-01 1.0000+00 2.0000+E00 5.0000Z-01 1.0000o+00 2.0000Z+00 8.00001+00 1.760B-03 1.7601-03 1.760B-03 1.290-03 8.00001+00 2.40001+O1 9.60001+01 2.4000B+01 9.6000R+01 7.2000E+02 4.2601-04 3.670B-04 3.150l-04 4.2601-04 3.6708-04 3.1501-04

.000E+00

.0001.00

.00OZ+00 3.500s-04 3.500B-04 3.5001-04

.000B+00

.0001+00

.000H+00

.0001+00

.0003+00

1. o0o0000 6.000R-01 4 000Z-01 TIME INTERVAL (hours)

COMPAMT A

MULTIPLIERS (IF APPLICABLE)

LEAK RATE RIc.rxLTIR COMPART B

MULTIPLIERS (IF APPLICABLE)

LEAK RATE RzC.FriLR COMPART C

MULTIPLIERS (IT APPLICABLE)

INTAKEB/BI RBC.F1LTHR FLOW MULT.

SPRAYED AREA TO UNSPRAYED

.00001.00 5.0000B-01 1.0000B.00 2.00001+00 8.00001+00

2. 4000R+01 9 6000z+01 5.00001-01

- 1.0000Z+OO 2.0000O+00 8.0000Z+00 2.4000X+01 9.6000B+01 7.2000E+02 1.O000+00 1.000Z+00 1.0001+00 1.0001+00 1.0001+00 1.000B+00 1.000,+00 1.000Z+00

1. 000B+00

1. 000+00 1.0001+00 1.0001.00

1. 000+00

1. 000E+00 1.0001+00

1. 0001.00 1.000+00Z+

1.000B+00 1.0001+00 1.0001+00 1.0001+00 1.000+00 1.0001.00 1.0001+00 1.0001+00 1.0001+00 1.0001+00 1.0001+00 1.o000+00 1.0001+00 1.0001+00 1.0003+00 1.0001+00 1.000R+00

1. 000e+00

1. 0001+00 1.0001+00 1.000C+00 1.0001+00 1.0001+00 1.000e+00

1. 000Z+00 1.O000+00 1.00O1.00

1. 0001+00 1.000Z+00 1.000Z+00 1.000+E00

1. 0001+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Altemative Source Term Methodology (2038 MWt)

A R EVA Prepared by: John N. Hamawi Document ID 32-5052589-01 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)

NUCLIDE BR 82M BR 82 BR 83 BR 84K BR 84 BR 85 BR 86 BR 87 GROUP 2

2 2

2 (CL) 7.89203+01 2.0420E+02 2.56703+03 1.3280E+02 4.7330E+03 5.B150.+03 4.35603+03

9. 92103+03 U88R-SPECIFIED SOURCE INVENTORY NUCLIDE GROUP (Ci)

IR 87 1

1.17503+04 KR 88 1

1.66203+04 KR 89 1

2.0960E+04 KR 90 1

2.0810E+04 1128 2

5.70203+02 1129 2

1.7930R-03 1130H 2

5.40203+02 1130 2

1.38303+03 NUCLIDE 1134 1135 1136K 1136 XZ131M XB133N XB133 XB135M GROUP 2

2 2

2 1

1 1

1 (CL) 3.8150C+04 3.18203+04 9.4460E+03 1.5440E+04 1.90505+02

1. 05203+03 3.41705+04 6.8250Rt03 BR 88 KR 83N KR 85M KR 85 2

1.13003+04 1

2.56708303 1

5.88003+03 1

8.5510E+02 1131 1132 S133 11343 2

2.71703+04 2

2.41103+04 2

3.4170E+04 2

4.07403i03 X3135 X3137 X3138 X3139 1

1.74403+04 1

3.00703B04 1

3.03703+04 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 NUCLIDE BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 KR 87 KR 88 RB 87 RB 88 RD 89 INVENTORY FOLLOWING GROUP (CL) 2 1.27613+02 2

2.4352E+00 2

1.10573-10 1

9.44453.00 1

1.45053+02 1

8.55013+02 1

2.47293-02 1

4.7443Z+01 3

3.6297E-11 3

5.2925E*01 3

1.6731B-25 2.4003o01 HOURS Or RADIOACTIVE GROWTH AND DECAY PRIOR TO RZLEASE NUCLIDE GROUP (Ci)

NUCLIDE GROUP (Ci)

SR 89 3

9.01503-01 XE133M 1

9.4669E.02 1128 2

2.5419Z-15 XE133 1

3.2869E+04 1129 2

1.79303-03 XE135M 1

4.1160E+02 1130N 2

3.69638-46 X3135 1

9.60503+03 1130 2

3.61473+02 XZ138 1

7.7776e-27 1131 2

2.49263+04 C9135 3

6.60143-06 2132 2

1.74193+01 CS137 3

7.2987Z-03 1133 2

1.5357+.04 C8138 3

8.23373-10 1134 2

2.1896Z-04 C8139 3

1.41358-43 1135 2

2.56973.03 BA137M 3

6.904S8-03 X3131M 1

1.96063+02 DA139 3

1.2700R-03

I A,

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

A R EVA Prepared by. John N. Hamawi Document ID 32.5052589-01 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 AR EVA 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 ID 32-5052589-01 Page 51 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.

A (Ci/m3)

DR 82 DR 83 BR 84 KR 83H KR 85M KR 85 KR 87 KR 88 1128 1129 1130H 1130 1131 1132 1133 1134 1135 XE131M XZ133M XR133 X1135H XZ9135 XE138 3 2191-05 6.143E-07 2.789B-17 4.765E-04 7.318B-03 4.3141-02 1.2 48-06 2.3941-03 6.412E-22 4.523B-10 9.324Z-53

9. 118-05 6.288B-03 4.394B-06 3.874E-03 5.523K-il 6.482E-04 9.891E-03 4.776Z-02 1.6581+00 2 077B-02 4.8416z-01 3.924B-31 CHEM-SPRAY IN COMP. A (Ci)

.0001+00

. 000e.00

. 0001o00 000E+00

.0001+00

. 0001+00

.000+00

. 000+00 0001+00

. 0001+00

.000+00

. OOO100

.000Z+00

.0001+00

.000+00

.00OX+00

.0001+00

.OOOE+00

.0001+00 REC.FILTER IN COMP.

A (Ci)

.0002+00

.0001+00

. 0001+00

.0001+00

. 0001+00

.000+00

.0001+00

.000+.00

.ooo0+00 000Z+00

.0001+00

.000+00 0001+00

.0001+00

.000+00 COMPARTH.

B (Ci/=3)

.0001+00

.OOO+00

.0001+00

.0001400

.0001+00

.OOO+OO

.OOO+00

.0001+00

. 0001+00

.000+00

.0001+00

. OOO+00

.oooe+00

.0001+00

.000oo00

.000o+00

.OOO+00 REC.FILTSR in COMP. n (CL)

.0001+00

.000N+00

.0001+00

.0001.00

.0001+00

.000E+00

.0001.00 8XH FILTER TO ATMOSP.

(C1)

.0001.00

.0001+00

.0001.00

.0001+00

.0001.00

.0001+00 0001.00

.OOO+00

.0001+00

.OOO+.00

.0001+00

.0002+00

.0001.00

.0001+00

.0001.00

.0001+00

.000Z+00

.OOO+00

.0001+00

.0008+00 COMPARSM.

C (Ci/m3)

.0001+00

.0008+00

.000X+00

.000Z+00

.OOO+00

.OOO+OO

.0001+00

.000oo00

.000N+00

.0001+00

.000Z+00

.0001+00

.OOO+00

.000X+00

.0001+00

.000+00

.0001+00

.000+00

.0001+00

.0001+00 INS. FILTER TO COMP.

C (Ci)

.000Z+00

.0001+00

.OOO+00

.0008+00

.0001+00

.OOO+00

.0001+00

.0008+00

.0001+00

.00O0+00

.0001+00

.000+00

.0001400

.000+00

.0001+00

.000+.00 REC.FILTER IN COMP. C (Ci)

.0001+00

. 0001+00

.OOO+00

.000+.00

.000+00

.0001+00

.0008+00

.0001+00

.000+00

.0001+00

.000+00

.OOO00

.0001+00

.000Z+00

.000+00

.0001+00 TOTALS GROUP GROUP GROUP 1

2 3

2.2753+00

1. 094-02

.0001+00

.OOOZ+00

.0001+00

.OOO+00

.0001+00

.000+00

.0001+00

.OOO+OO

.000+00

.0001+00

.0008+00

.0001+00

.000E+00

.0001+00

. 000o+00

.000+00

.0001+00

.000+00 GRND.TOT 2.2851+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 PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident ABased on the Alternative Source Term Methodology (2038 MWI)

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 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 NUCLIDE BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 RR 87 KR 88 1128 1129 1130M 1130 1131 1132 1133 1134 1135 XZ131M XZ133M X8133 X113SM XZ135 XZ138 TOTALS GROUP 1

GROUP 2

GROUP 3

GRND.TOT REZL. RATE (Cl/hr) 2.552E+00 4*870Z-02 2.211Z-12 3.7783+01 S.8023+02 3.420E+03 9.8923-02 1.898B+02 5.084E-17 3.5868-05 7.3933-48 7.229Z00 4.9851.02 3.484R-01 3.0711+02 4.379B-06 5.139B+01 7.843E+02 3.787Z+03 1.315Z105 1.6461+03 3.842N+04 3.111B-26 1.8031+05 8.672Z+02

.OOO+00 1.8123+05 WITHOUT DECAY INTRV REL (CL)

.0003+00

.0001+00

.0003400

.0003+00

0001.00

.000z.00

.0001+00

0003.00

.000E+00

.0001+00

.000H400

.0001.00

. OOO+00

.0001+00

.0003+00

.0OOO+00

.OOO+00

.0003+00

.0001.00

. 0003.00

.0003.00

.0003+00

.0003.00

.000E+00

.OOOE+00 IN TRANSIT CVNL. REL (Cl)

.000v+00

.000Z+00

.0008+00

.000+00

.0008+00

.0003+00

.0003400

.0003+00

.0003.00

.0001.00

.000E+00

.0003+00

.0001+00

.0003+00

.0001.00

.000Z+00

.0003.00

.000Z+00

.0008+00

.0003+00

.0008+00 CLOUD CONC (Ci/m3) 1.2481-06 2.3811-08 1.081Z-18 1.8471-05 2.837Z-04 1.672Z-03

4. 836B-08 9.278Z-05 2.4853-23 1.753B-11 3.6143-54 3.5341-06 2.4371-04 1.703Z-07 1.502B-04 2.141Z-12 2.513B-05 3.834E-04 1.851Z-03 6.4281-02 8.049B-04 1.8783-02 1.521Z-32 8.817Z-02 4.2401-04

.0OOO+00 8

8.859Z-02 REL. RATE (Cl/br) 2.5528+00 4.8701-02 2.2111-1.2 3.778Z+01

5. 8023+02 3.4203.03 9.892Z-02 1.8981+02 5.084E-17 3.586Z-05 7.393Z-48 7.229E+00 4.9851+02 3.4843-01 3.0711+02 4.3793-06 5.139Z+01 7.843Z+02 3.787Z+03 1.3153+05 1.6461+03 3.8423+04 3.111E-26 1.8033+05 8.6723+02

.0003.00 1.812Z+05 INTRV REL (Ci)

.000+00

.000R+00

.000+00

.000o+00

.0008+00

.000+00

.ooo0+00

.0008+00

.000z+0o

.0001+00

.0003.00

.0003+00

. 0001+00

.000+00

.0003+00

.0001+00

.0OOO+00

.0003.00

.000+00

.0003+00

.0001+00

.0008+00

.000Z+0O

.0001+00

.000+00 CUML. REL (Cl)

.0003+00

.OOOE+00

.OOOB+00

.0003+00

.OOO+00

.0003,00

.0001+00

.0003+00

.0003.00

.0001+00

.0001.00

.0001+00

.0OOO+00

.0001+00

.0003+00

.0OOO+00

.0003+00

.0001+00

.0003+00

.000z+00

.0001+00

.0003.00

.0001.00

.0003400

.0003+00

.0003+00 CLOUD CONC (Ci/m3) 1.2489-06 2.381Z-08 1.081B-18 1.8471-05 2.837Z-04 1.672Z-03 4.836B-08 9.2781-05

2. 4858-23 1.753Z-11 3.614E-54 3.534Z-06

2. 4371-04 1.7033-07 1.502B-04 2.1413-12 2.513Z-05 3.8341-04 1.8513-03 6.4283-02 8.0493-04 1.8788-02 1.521B-32 8.8171-02 4.2401-04

.000o+00 8.859Z-02 WITH.0003+00 hra IN-TRANSIT DECAY NOTEi THE ATMOSPHERIC CONCENTRATION OF RADIOACTIVITY 1S BASED ON A DISPERSION FACTOR (X/Q) OF 1.7603-03 (sae/m3)

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. Hamawt Document ID 32.5052589-01 Page 53 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.

A (Ci/m3)

BR 82 BR 83 BR 84 KR 83M XR 85M KR 85 KR 87 KR 88 RD 87 RD 98 1128 1129 X130H 1130 1131 1132 1133 1134 1135 XB131M XB133N XB133 XZ135M XE135 XZ138 CS13S CS138 4.3124-06 7.191Z-08 1.963Z-18 6.190Z-05 9.166Z-04 5.838Z-03 1.286Z-07 2.867Z-04 1.2441-22 2.077Z-04 3.775Z-23 6.121B-11 1.2521-54 1.200E-05 8.4941-04 5.115-07 5.156Z-04 5.0341-12 8.3251-05 1.3441-03 6.484X-03 2.2471-01 8.198B-03 6.501B-02 1.2243-32 1.106E-12 1.226Z-32 CEZY-SPRAY IN COMP. A MCU)

.000v+00

.000z+00

. OOO+OO

.OO0.OO

.0001.00

.000+00

.0001.00

.*000100

.0001+00

.00OZ+00

.000B+00

. 0001+00

.000+.00

.0001+00

000+.00

.OOOE+00

.0001+00

.0001.00

.000E+00

.0001+00

.OOO+OO

.0001+00

.000+00

.0001+00

.OOO+.00

.OOOE+00 RRC.FILTER IN COMP. A (CL)

.0001Z00

.0001+00

.0001.00

. 0001+00

.0001+00

.000+00

.0001+00

.OOO+00

.0001.00

.000+.00

.0001+00

.0001.00

.000+00

.0001+00

.OOO+00

.0oooe00

.OOO+00

.0001+00

.OOO+00 COMPARTS.

B (CL/mn3)

.0001.00

.0001 +00

.0001+00

.oooe+00

.0001+00

.000+Z00

.000X+00

.000Z+00

.OOO+00

.000oo00

.000o+00

.0003.00

.0ooo+00

.000o+00

.OOO+00

.0001+00

.000z+00

.0001+00

.000X+00

.OOO+00

.OOO+OO

.0008+00

.0001+00

.0001+00 REC.FILTER IN COMP. B (CL)

.0001+00

.000.+00

.OOOB-00

.0001.00

.0001+00

.00O0100

.0001+00

.000X+00

.0001+00

.0003+00

.0001+00

.OOO+00

.0001+00

.OOO+00

.0001.00

.OOO+100

.0001.00

.OOO+00

.0001+00

.000+.00

.0001+00

.oooe+00 MM.FILTER TO ATMOSP.

(CL)

.000-0

.0001+00

.OOO+00

.0001+00

.0001.00

.OOOE+00

.0001o00

.000w.00

.OOON+OO

.0001+00

.0001,00:

.0001.00

.0003+00

.0001.00

.OOO+00

.0001.00.

.OOOE+00

.0001+00

.0001.00

.0001+00

.0001.00

.0001+00

.000z+00 COMPART5.

C (Cd/m3) 2.7061-07 4.5109-09 1.231Z-19 3.4851-06 5.7491-05 3.6618-04 8.0638-09 1.7988-05 7.804E-24 1.3031-05 2.3681-24 3.839B-12

7. 852E-56 7.526Z-07 5.3271-05 3.208B-08 3.234B-O5 3.1571-13 5.2211-06 8.398Z-05 4.0381-04 1.4051-02 1.349E-04 3.994E-03 7.677B-34 6.938E-14 7.6899-34 INS. FILTER TO COMP. C (Ci)

.0001+00

.000oo00

.0001+00

.0ooo+00

.000o+00

.0001+00

.OOOE+00

.0001+00

.OOOo00

.0001+00

.000K+00

.0001+00

.0001+00 REC.FILTER IN COMP.

C (CI)

.0001+00

. OOO+00

.000x+00

.0001+00

.000+00

.0001+00

.000x+00

.OOO100

.0001+00

.Ooo0+00

.000+.00

.OOOE+00

.OOO+100

.0001+00

.OOO+00

.0001+00

.000E+00

.0001+00

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Termn Methodology (2038 MWt)

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 GROUP 2 1.465E-03

.OOO+00

.000+00

.OOO+00 GROUP 3

2.077Z-04

.0003+00

000E.0O

.OOOZ+0 oRND.TOT 3.1453-01

.OOO00

.oooe0oo

.oooz0oo THE COMPARTMENT VOLUMES (A,

B AND C)

IN THIS TABLE AR.7

.OOOE00

.000+00

.OOOZ+00

.OOOE+00 1.9823.04

.000,+00 2.911Z-02

,000+00 9.189B-05

.0003+00 1.303Z-05

.OOO+00 1.9223-02

.0003+00 9.707Z+02 (m3)

. 000+00

. 0003+00

.0003+00

.000+00

.000o+00

. ooo0+00

.*000300

PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 Page 55 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 NUCLIDE BR 82 BR 83 BR 84 KR 83M KR 85M

]R 85 XR 87 XR 88 RB 87 RB 88 1128 1129 1130M 1130 1131 1132 1133 1134 1135 XS131M S8133M XZ133 XE135M XE135 XZ138 CS135 C8138 REL.

RATE (Cl/hr) 3.4201-01 5.702Z-03 1.5568-13 4.9085+00 7.2683+01 4.6289+02 1.019Z-02 2.273E401 9.865Z-18 1.647EO01 2.993Z-18 4.853E-06 9.926E-50 9.5143-01 6.735E+01 4* 055Z-02 4.088X.01 3.991B-07 6.6001.00 1.0663+02 5.1413+02 1.7823.Q4 6.5003+02 5.1543+03 9.705Z-28 8.770Z-08 9.7201-28 XNTRV REL (CL) 5.499Z-01

1. 0023-02 3.873Z-13 7.898E+00 1.2223+02 7.3933+02 1.952Z-02 3.936Z+01 5.751Z-18 1.1913+01 8.446R-18 7.7523-06 8.4603-49 1.5483+00 1.077E+02 7.1561-02 6.601X+01 8.308Z-07 1.0911.01 1.6963+02 8.1843402 2.842E+04 4.595E+02 8.248E+03 4.346Z-27 4.9538-08 8.771Z-28 CUML.

REL (Cl) 5.499B-01 1.002E-02 3.873Z-13 7.898E+00 1.222Z+02 7.3935+02 1.952Z-02 3.9363.01 5.7511-18 1.1913+01 8.4461-18 7.7523-06 8.460E-49 1.5485+00 1.0773+02 7.156B-02 6.6013+01 8.308Z-07

1. 0913+01 1.6961+02 8.1841402 2.8421+04 4.5951+02 8.2485+03 4.346B-27 4.853Z-08 8.771Z-29 CLOUD CONC (CL/m3) 1.6725-07 2.787E-09 7.609Z-20 2.3993-06 3.553Z-05 2.263E-04 4.9833-09 1.1118-05 4.8233-24 8.0503-06 1.4632-24 2.3733-12 4.8533-56 4.651E-07 3.2923-05 1.983B-08 1.9993-05 1.9515-13 3.227Z-06 5.211Z-05 2.513Z-04 8.7103-03 3.178Z-04 2.5205-03 4.7453-34 4.2985-14 4.7525-34 WITH

.0003+00 hr. IN-TRAN8IT DECAY REL. RATS XNTRV REL CUML. REL CLOUD CONC (CL/hr) 3.4203-01 5.702Z-03 1.556Z-13 4.9083+00 7.2683+01 4.6285+02 1.019E-02 2.2733+01 9.865E-18 1.647Z+01 2.9933-18 4.8533-06 9.9268-50 9.5141-01 6.7353+01 4.0553-02 4.0883+01 3.991E-07 6.600z+00 1.0663+02 5.1413+02 1.7821+04 6.5005+02

5. 1541+03 9.7058-28 8.7708-08 (CO) 5.4993-01 1.0023-02 3.873E-13

7. 899E.00 1.222Z302 7.3931+02 1.9521-02 3.9361+01 5.7513-18 1.1913+01 8.4465-18 7.7523-06 8.460E-49 1.548Z400 1.0775+02 7.1S6Z-02 6.6013+01 8.308Z-07 I.0915+01 1.6962+02

8. 1841+02 2.8425+04 4.595Z+02 8.2483+03 4.3468-27 4.8535-08 (CM) 5.4993-01 1.0025-02 3.8731-13 7.8985+00 1.2223+02 7.3933+02 1.9525-02 3.9363+01 5.7513-18

1. 1913+01 8.4463-18 7.7523-06 8.4601-49 1.5481+00 1.0778+02 7.1563-02 6.6013+01 8.308Z-07 1.0915+01 1.6963+02 8.1843+02 2.8425+04

4. 595Z+02 8.248Z+03 4.3465-27 4.8531-08 (Ci/m3) 1.6723-07 2.787Z-09 7.609E-20 2.399Z-06 3.5533-05 2.2633-04 4.9835-09 1.111-05 4.8233-24 8.0508-06 1.4638-24 2.373Z-12 4.8533-56 4.6511-07 3.2921-05 1.9835-08 1.9995-05 1.951Z-13 3.227Z-06 5.2115-05 2.5135-04 8.710Z-03 3.1783-04 2.5203-03 4.745E-34 4.28S3-14 9.7205-28 8.7715-28 8.7718-28 4.7525-34

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-505258901 Based on the Alternative Source Term Methodology (2038 MWt)

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)

(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 ARE VA 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 ID 32-5052589-01 Page 57 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 COMPARTMENT C Beta Air DOSE RATE NUCLIDZ (rad/hr)

BR 82 6.6893-05 BR 83 2.577z-06 BR 84 2.6918-16 KR 83N 2.399Z-04 KR 85M 2.610B-02 KR 85 1.631Z-01 KR 87 1.s999-05 KR 88 1.16SE-02 RB 87 1.546R-21 RB 88 4.786Z-02 1128 3.149Z-21 1129 4.3561-10 1130M

.0001400 1130 3.978s-o0 1131 1.8161-02 1132 2.8261-05 1133 2.3613-02 1134 3.4941-10 1135 3.408E-03 XB131M 2.148R-02 XB133M 1.381z-01 XE133 3.391E+00 XZ135M 2.3401-02 X3135 2.253s+00 X1138 9.183E-31 C8135 8.3031-12 C8138 1.6513-30 EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (INTERVAL DOSES ARM FROM.0000R+00 TO 5.0000R-01 hrD)

(CONTINUOUS OCCUPANCY)

Beta Air SNTVL DOs (rad) 2.7931-05 1.1392-06 1.489R-16 1.058s-O4 1.121Z-02 6.782Z-02 8.8633-O6 5.099Z-03 3.9111-22 1.399Z-02 1.8s93-21 1.8111-10

.00O1+00 1.6733-04 7.5583-03 1.252B-05 9.8873-03 1.721E-10 1.4483-03 8.928z-03 5.7503-02 1.4113E00 1.0053-02 9.4783-01 7.s353-31 2.0283-12 5.611B-31 Gata Air Gaa Air Tot. Skin DOSE RATE INTVL DOS DOSE RATE (rad/hr)

(rad)

(rem/hr) 1.655B-05 6.908s-06 3.487Z-05 8.2333-10 3.6303-10 1.087R-06 4.316Z-18 2.3883-18 1.4223-16 7.8113-06 3.4463-06 1.6231-06 2.508Z-04 1.077B-04 1.071B-02 1.972Z-05 8.2023-06 6.379s-02 1.2903-07 6.022e-08 9.923Z-06 7.0233-04 3.074E-04 5.7841-03

.OOO+00

.000+00 3.274z-22 1.664E-04 4.8633-05 2.5613-02 5.4863-24 3.2973-24 1.554E-21 1.802X-11 7.4953-12 2.3521-11 3.439Z-55

.4373-55 2.7923-55 3.8553-05 1.6223-05 1.9961-04 5.0733-04 2.1111-04 6.6251-03 1.7213-06 7.624R-07 1.440Z-05 4.717R-04 1.9753-04 1.094B-02 1.9023-11 9.3683-12 1.8141-10 1.761z-04 7.486e-05 1.6203-03 3.0323-04 1.2603-04 4.7518-03 1.698E-03 7.0723-04 4.6938-02 2.770Z-02 1.1533-02 5.454E-01 1.5253-03 6.552E-04 1.171Z-02 2.3343-02 9.8193-03 9.53SE-01 1.789z-32 1.468R-32 4.4853-31

.0003.00

.000Z+00 8.372E-13 3.8383-32 1.30S1-32 8.716R-31 Tot. Skin XNTVL DOS (rem) 1.456z-05 4.8051-07 7.8663-17 7.1593-07 4.601B-03 2.653B-02 4.632E-06 2.531Z-03 8.283e-23

7. 484-03 9.3371-22 9.7823-12 3.6021-55 8.396z-05 2.757z-03 6.378s-06 4.5823-03 9.937E-11 6.88S3-04 1.9753-03 1.9548-02 2.2693-01 5.030R-03 4.011B-01 3.680X-31 2.0451-13 2.9631-31 Thyroid DOSE RATS (rem/hr) 1.2203-05 6.267E-10 3.437z-18 2.920z-08 1.742E-04 1.579Z-05 1.007Z-07 5.5441-04

.0001Z00 1.337B-04 3.9833-24 4.224B-12

.000+00 2.8053-05 3.6073-04 1.265s-06 3.4113-04 1.410E-11 1.3423-04 8.8381-os B.il43-04 1.379X-02 1.0793-03 1.6643-02 1.3743-32

.0003+00 2.9442-32 Thyroid INTVL DOS (rem) 5.095R-06 2.7703-10 1.9011-18 1.28S1-08 7.4823-05 6.5651-06 4.6991-08 2.4263-04

.0008+00 3.906Z-05 2.394B-24 1.7563-12

.000Z+00 1.180Z-05 1.501B-04 5.605S-07 1.4281-04 6.9461-12 5.703Z-05 3.674B-05 3.462R-04 5.7363-03 4.634E-04 7.0003-03 1.128Z-32

.000Z00 1.001-32 8ff D.E.

DOSE RATE (rem/hr) 1.2201-05 6.300Z-10 3.4041-18 6.8123-08 1.7783-04 1.592Z-05 1.0041-07 5.490E-04

.0003+00 1.333Z-04 4.0123-24 4.1581-12

.OOOZ+00 2.805z-05 3.6271-04 1.2653-06 3.422E-04 1.4103-11 1.3373-04 8.793Z-05 8.3751-04 1.424B-02 1.0798-03 1.C670-02 1.374E-32

.0003+00 2.94Z1-32 Eff D.E.

INTVL DOS (rem) 5.095R-06 2.7843-10 1.883z-18 3.005z-08 7.6353-05 6.6213-06 4.688R-08 2.4033-04

. 0001Z00 3.8943-05 2.4121-24 1.7293-12

.0003.00

1. 180Z-05 1.509E-04 5.605E-07 1.433E-04 6.946B-12 5.6812-05 3.6551-05 3.4883-04 5.9263-03 4.6343-04 7.059B-03 1.1283-32

.OOO300 1.001Z-32

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by, John N. Hamawi Document ID 32-5052589-01 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 COMPARTMENT C EXTERNAL RADIATXON EXPOSURt DUE TO AIR8ORN8 RAD!OACT=VITY (INTERVAL DOSES ARE FROM.00001i00 TO 5.OOOOE-01 brs)

(CONTINUOUS OCCUPANCY)

Beta Air DOSs RATE (rad/hr)

GROUP 1 6.028E+00 GROUP 2 4.568B-02 GROUP 3 4.786B-02 GRND.TOT 6.122E+00 CUM. TOTAL FROM T.0 Lungs DOSE RATE (rem/hr)

GROUP 1 3.0558-02 GROUP 2 8.554Z-04 GROUP 3 1.3139-O0 GRND.TOT 3.1538-02 CUM. TOTAL FROM TaO Beta Air INSVL DOS (rad) 2.520K+00 1.910B-02 1.399Z-02 2.5531+00 2.5531+00 Lungs INTVL DOS (rem) 1.281Z-02 3.5828-04 3.836Z-OS 1.3211-02 1.321Z-02 Gamea Air DOSE RATE (rad/hr) 5.555Z-02 1.212Z-03 1.6641-04 5.693Z-02 R.Marrow DOSE RATE (rem/hr) 2.7301-02 8.2661-04 1.3093-04 2.825Z-02 Ga=a Air INTVL DOS (rad) 2.326R-02 5.073E-04 4.8631-05 2.3828-02 2.3828-02 R.Marrow INTVL DOS (rem) 1.145E-02 3.4611-04 3.8241-05 1.184E-02 1.184B-02 Tot. Skin DOSE RATE (rem/br) 1.6431+00 1.9441-02 2.5618-02 1.6881+00 lone our DOSE RATE (rem/br)

B.837B-02 1.510B-03 1.8321-04 9.006Z-02 Tot. Skin INTVL DOS 6.883R-01 8.1338-03 7.4841-03 7.039Z-01 7.039B-01 Done Bur INTVL DOS (rem) 3.698Z-02 6.3171-04 5.3541-05 3.7671-02 3.7671-02 Gonads DOSE RATE (rem/br) 3.395S-02 8.5941-04 1.293E-04 3.494E-02 Thyroid WDO8 RATE (rem/br) 3.317i-02 8.7751-04 1.3371-04 3.418E-02 Gonads rNTVL DOS (rem) 1.423Z-02 3.5983-04 3.778Z-05 1.463B-02 1.4631-02 Thyroid

.INTVL DOS (rem) 1.391Z-02 3.674E-04 3.906E-05 1.4311-02 1.4311-02 Breast DOSE RATE (rem/hr) 3.98SZ-02 9.8181-04 1.4551-04 40*

098s-02 Rp-aindr DOW8 RATE (rem/hr) 2.901B-02 8.161B-04 1.273E-04 2.996Z-02 Breast INTVL DOS (rem) 1.6701-02 4.1113-04 4.2531-05 1.7152-02 1.715B-02 Remainidr ITNTVL DOS (rem) 1.217Z-02 3.417Z-04 3.720B-05 1.255-02 1.2551-02 Bff D.C.

DOSE RATE (rem/hr)

GROUP 1 3.377Z-02 GROUP 2 8.8021-04 GROUP 3 1.333Z-04 ORND.TOT 3.478B-02 CuM. TOTAL FROM TaO 8ff D.E.

INTVL DOS (rem) 1.416E-02 3.685E-04 3.8941-03 1.45G6-02 1.4561-02 TID Thy DOSE RATE (rem/hr)

.000H+00

.0001E00

.0001.00

. 000100 TID Thy INTVL DOS (rem)

.0003+00

.000N.00

.0001+00

.000.+00

.000+0O0 RG11O9WB DOS RATE (rem/hr) 5.000Z-02 1.1381-03

.0001+00 5.1141-02 R011O9WB INTVL DOS (rem) 2.094B-02 4.7653-04

.0001+00 2.1421-02 2.1421-02

A ARE VA 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 59 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 COMPARTMENT C NUCLIDS BR 82 BR 83 BR 84 KR 83M KR 85N KR 85 KR 87 KR 88 RB 87 RS 88 X128 I129 1130M 1130 1131 1132 1133 1134 1135 XB131M XZ133N XE133 XZ135M Xl135 XE138 CS135 CS138 RADIATION EXPOSURE DUZ TO INHALATION (INTERVAL DOS8 ARE FROM

.00001400 TO 5.00003-01 bra)

Thyroid DOSE RATE (rem/hr) 2.5993-04 2.397B-08 1.7918-18

.000X+00

.0005+00

.0003+00 2.6053-20 8.320Z-05 5.895B-22 2.7923-05

.0003+00 6.982E-02 7.2523+01 2.6023-04 7.3273.00 4.239Z-10 2.059B-01

.0003+00

.000Z+00

.0003+00

.000Z+00

.0003+00 3.881R-10 1.26CE-32 Thyroid INTVL DOS (rem) 1.0853-04 1.059B-08 9.9083-19

.0003+00

.000.E00

.000X+00

.0003+00 6.590Z-21 2.4313-05 3.5433-22 1.161Z-05

.oooe+00 2.937B-02 3.0183+01 1.153B-04 3.0688+00 2.088Z-10 8.752B-02

.000X+00

.0003+00

.000E+00

.0003+00

.000E+00

.0003+00 9.4813-11 4.351B-33 Zff D.E.

DOSE RATS (rca/hr) 5.2103-04 5.067B-07 1.498Z-17

.000o+00

.0005+00

.00oz+00

.0003+00 3.180Z-20 1.372E-03 1.4133-22 8.3943-07

.00O+00 2.505Z-03 2.2083+00 1.5403-05 2.382E-01 5.226B-11 8.0813-03

.0003+00

.000Z+00

.0003+00

.000Z+00 3.9783-10 9.8223-32 8ff D.E.

INTVL DOS (rem) 2.175-04 2.240E-07 8.2883-18

.0003+00

.000E+00

.0003+00

.0005+00

.000E+00 8.0443-21 4.0113-04 8.492E-23 3.490E-07

.000E+00 1.054E-03 9.188Z-01 6.824E-06 9.973B-02 2.574E-11 3.435R-03

.00O0300

.0003+00

.0000+oo

.0003.00

.0003+00 9.718E-11 3.339E-32 (CONTINUOUS OCCUPANCY)

.e

A AR EVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWQ Prepared by-John N. Hamawi Page 60 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 COMPARTMENT C RADIATION ExPOsURE DUE TO INHALATION (INTERVAL DOSES ARE FROM.00003E00 TO 5.0000B-01 br.)

Gouada DOSE RATE (rem/hr)

(CONTINUOUS OCCUPANCY)

Gonada INTVL DOs (re=)

.000E+00 4.153e-03 2.3253-05 Breast DOSE RATE (rem/hr)

.0001+00 2.501X-02 8.6843-05 8reaut INTVL DOS (rem)

.0003E00 1.043E-02 2.53se-05 GROUP I

GROUP 2

GROUP 3

. 000o00 9.9S13-03 7.9553-05 GRND.TOT CUM. TOTAL FROM T-O 1.0031-02 4.1763-03 4.176Z-03 2.5101-02 1.0453-02 1.045E-02 Lungs DOSE RATE (rem/hr)

Lunga INTVL DOS (rem)

.0003+00 1.2601-01 2.609B-03 R.Marrow DOSE RATE (rem/br)

.000.E00 2.063B-02 8.8063-05 R.Marrow rNTVL DOS.

(rem)

.0001+00 8.601E-03 2.5738-05 Bone our DOSE. RATR (rem/hr)

.0001+00 1.8913-02

.s9273-05 Done Bur INTvL DOB (rem)

.OOO+00 7.882B-03 2.609E-05 Thyroid DO8E RATE (rem/hr)

.OOO+00 8.0133+01 8.3203-05 Thyroid nTV.

DOS (rem)

.0003+00 3.3363+01 2.4313-05 Remwandr DOSE RATE (rem/hr)

.000Z+00 2.9333-02 8.3911-04 Ramaindr INTVL DOS (rem)

.0003.00 1.2248-02 2.4493-04 GROUP 1

GROUP 2

GROUP 3

.0003.00 3.018B-01 8.9273-03 GRND.TOT 3.107B-01 CUM. TOTAL FROM T.0 zff D.E.

DOSE RATE (rem/hr) 1.28s6-01 1.2986-01 Bff D.E.

INTVL DOS (rem)

.000E+00 1.0233.00 4.011E-04 2.0723-02 8.6273-03 8.627z-03 1.8s9s-02 7.9081-03 7.908B-03 8.0133+01 3.3361+01 3.017Y-02 1.2483-02 3.3361+01 1.248Z-02 TID Thy DOSE RATE (rem/hr)

.0001+00 1.1653+02

.0ooo0 00 TID Thy INTVL DOS (remn)

I GROUP 1

GROUP 2

GROUP 3

.0001+00 2.457E+00

1. 372B-03

.000.+00 4.851+,01

.0001+00 GRND.TOT 2.4591+00 1.0243+00 CUN. TOTAL FROM TnO 1.0241+00 1.1653+02 4A.51B+01

4. 9513+01

A AR EVA 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 ID 32-5052589-1 Page 61 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 COMPARTEENT C TOTAL RADIATION EXPOSURES (AIR IMMERSION PLUS INHALATIONh (CONTINUOUS OCCUPANCY)

Beta Air DOSE RATE T (hours)

(rad/hr)

.00003+00 5.0000B-01 1.00003+00 2.00003+00 8.0000z+00 2.40003+01 9.6000z+01 7.2000c+02

.000B+00 6.122R+00 3.3683+00 6.830Z-0l 2.9083-02 2.6703-03 1.0543-04 1.1273-06 Beta Air SNTVL DOS (red)

.000R+00 2.5533+00 2.3793+00 1.6973+00 5.8733-01 9.561Z-02 4.10&4-02 5.0303-03 Gonadn INTVL DOS (rem)

.oooe+00 l.880Z-02 1.751-02 1.285E-02 6.297E-03 1.337E-03 3.5403-04 2.356E-05 Beta Air CUM. DOSE (red)

.0003+00 2.5533+00 4.9323+00 6.6283+00 7.2153+00 7.3113+00 7.3523+00 7.3573+00 Gonads CUM. DOSE (rem)

.0003+00 1.880B-02 3.631Z-02 4.9163-02 5.5463-02 5.680E-02 5.7153-02 5.717E-02 Gsam Air DOSE RATE (red/hr)

.000+00 5.6933-02 3.1633-02 7.1963-03 6.6123-04 4.917Z-05 9.811B-07 1.591E-08 Breast DOSE RATE (rem/hr)

.000B+00 6.6083-02 3.6573-02 7.8743-03 5.1963-04 3.7523-05 5.9953-07 7.1423-09 Gamma Air INTVL DOS (red)

.000B+00 2.382Z-02 2.2183-02 1.6423-02 8.6873-03 1.9763-03 5.7283-04 S.7793-05 Breast INTVL DOS (rem)

.0003+00 2.76O0-02 2.572E-02 1.871E-02 8.0913-03 1.5373-03 4.14&3-04 2.9913-05 Gamek Air CUM. DOSE (red)

.00O+00 2.3823-02 4.6003-02 6.2413-02

7. l103-02 7.3093-02 7.365E-02 7.371Z-02 Breast CUM. DOSE (rem)

.0003+00 2.760B-02 5.332Z-02 7.2043-02 8.0133-02 8.1663-02 8.2089-02 8.2113-02 Gonadt DOSE RATE T (hours)

(rem/hr)

.00003+00 5.0000o-01 1.0000B+00 2.00003+00 8.0000e+00 2.4000E+02 9.6000E+01 7.20003+02

.OOO+00 4.497Z-02 2.492E-02 5.5373-03 4.5212-04 3.248E-05 4.*884-07 5.4213-09 Tot. Skin DOSE RATE (rem/hr)

.0003+00 1.688R+00 9.2783-01 1.930Z-01 1.136Z-02 8.690e-04 1.939E-05 2.493Z-07 Lungs DOSE RATE (rem/hr)

.0003+00 3.423E-01 1.8843-01 3.620B-02 4.4083-04 3.1043-OS 3.8943-07 3.167Z-09 Thyroid DOSE RATE (rem/hr)

.000+00 8.0163+01 4.4113+01 8.4173.00 6.821Z-04 3.261B-05

4.552B-07

4. 6393-09 Tot. Skin INRVM DOS (rem)

.0003+00 7.039B-01 6.555B-01 4.6973-01 1.8853-0Ol 3.5163-02 1.0538-02 1.009Z-03 Lungs INTVL DOS (rem)

.0003+00 1.4183-01 1.332B-01 9.3763-02 2.356E-02 1.294E-03 3.2599-04 1.6373-05 Tot. Skin CUM. DOSE (rem)

.0003+00 7.0398-01 1.3593+00

1. 829E+00 2.018F+00 2.0533+00 2.0633+00 2.064R+00 Lungs CVM.

DOSE (rem)

.0003+00 1.4183-01 2.751Z-01 3.688E-01 3.9243-01 3.937E-01 3.940B-01 3.9403-01 R.Marrow DOSE RATE T (hours)

(rem/hr)

.00003+00 5.00008-01 1.0000R+00

2. 0000E+00 8.00003+00 2.40003+01 9.60003+01 7.2000E+02

.OOO+00 4.897Z-02 2.7113-02 S.9OOB-03 4.194E-04 2.920o-os 3.2383-07 2.6933-09 R.Marrow INTVL DOS (rem)

.OOO+00 2.047E-02

1. 9063-02 1.391E-02 6.2833-03 1.2288-03

2. 9853-04 1.3713-05 R.Marrow CVM.

DOSE (rem)

.000Z.00 2.047E-02 3.9538-02 5.344z-02 5.972Z-02 6.0953-02 6.1253-02 6.126Z-02 Bone Sur DOSE RATE (rem/hr)

.0003+00 1.091E-Ol 6.0323-02 1.3003-02 8.8003-04 6.73&4-05 1.4403-06 1.2573-08 Bone Sur INTV DOS (rem)

.0003+00 4.557B-02 4.2443-02 3.087E-02 1.35OB-02 2.6643-03 8.165B-04 6.269Z-05 Bone Sur CUM. DOSE (rem)

.OOOZ+00 4.5S78-02 8.8013-02 1.189B-01 1.3243-01 1.3503-01 1.3598-01 1.359B-01 Thyroid INTVL DOS (rem)

.0003+00 3.3383+02 3.1173+01 2.195E+01 4.8163+00 1.4773-03 3.4963-04 2.1093-05 Thyroid CUM. DOSE (rem)

.0003+00 3.3383+01 6.4553+01 8.6503+01 9.1323+01 9.1323+01 9.132Z+01 9.132E+01

A AR EVA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N. Hamawi Page 62 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 COMPART11ENT C TOTAL RADIATION EXPOSURES (AIR IMBRSION PLUS UNHALATION)

(CONTINUOUS OCCUPANCY)

Remaindr DOSE RATE S (hours)

(re=/Ur)

. 00003+00 5.00003-01 1.0000B+00 2.0000Z+00 8.0000x+00 2.4000z+01 9.60003+01 7.20003.02

. oOO+OO 6.013B-02 3.329Z-02 7.052E-03 4.2001-04 2.959Z-05 3.6903-07 3.215Z-09 Rem-indr ImTVL DOS (rem)

.OOO+00 2.503Z-02 2.3423-02 1.696s-02 6.934N-03 1.2343-03 3.101B-04 1.5973-OS RO1109W3 NTVZL DOS (rem)

. 000+00 2.142B-02 1.992Z-02 1.4763-02 7.958z-03 1.6243-03 5.0813-04 3.305Z-05 Remaindr CUM. DOSE (re)

. 0003Z00 2.503B-02 4.845E-02 6.5415-03 7.235B-02 7.3585-02 7.3099-02 7.391E-02 3ff D.H.

DOSE RATE (rem/br)

.0003+00 2.4933.00 1.372R300 2.626Z-01 4.662B-04 3.2823-05 4.6663-07 4.6153-09 Eff D.E.

INTVL DOS (rem)

. 000300 1.0383400 9.697Z-01 9.833E-01 1.5333-01 1.3608-03 3.536N-04 2.133B-05 3ff D.E.

CUM.

DOSE (rem)

.0003+00 1.0389+00 2.0083+00 2.69 1+00 2.8443+00 2.8463+00 2.8463+00 2.8463+00 TID Thy DOSE RATE (rem/hr)

.000Z+00 1.1653+02 6.4033.01 1.2203+01 3.2253-04 1.9981-16 2.6703-71

.oooe000 TID Thy INTVL DOS (rem)

.0003+00 4.8513.01 4.5273+01 3.1843+01 6.9663+00

1. 8353-04 1.138Z-16 1.5273-71 TID Thy CUM.

DOSB (rem)

.0003+00 4.851z+01 9.378O+40 1.2563+02 1.3263+02 1.3263+o2 1.3263+02 1.3261+02 RO1109W3 DOSE RATE T (hours)

(rem/hr)

.OOOO+.00 5.00003-01 1.00003+00 2.00003+00 8.00003+00 2.40003+01 9.60003+01 7.20003+02

.0003+00

5. 114-02 2.8403-02 6.496E-03 6.1283-04 4.4963-05 7.6153-07 6.6413-09 RO1109WB CUM.

DOSE (rem)

.0003+00 2.142E-02 4.1343-02 5.610B-02 6.4053-02 6.583Z-02 6.6393-02 6.642B-02

A AREVA 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 ID 32-5052589-01 Page 63 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 RECEPTOR/ORGAN Beta Air (rad)

Gm-a Air (rad)

Tot. skin (rem)

IBeta Cont. Mt))

Gonads (rem)

Breast (rem)

Lungs (rem)

[Inhalation pi)I R.Karrow (rem)

Bone Sur (rem)

Thyroid (rem)

CInhalation

") I Remaindr (rem)

Eff D.E.

(rem)

(Inhalation (%)]

TID Thy (rem)

R0l1O9WB (rem)

TOTAL RADIATION EXPOSURES (AS APPLICABLE)

CONTINUOUS OCCUPANCY COMPARTMENT A COMPARTMS N

B (Remispher)

(Spherical)

.0003.00

.000E+00

.0001+00

.0008+00

.000Z+00

.000B+00 C

.001 I

.001

.0008+00

.0001.00

.000H+00

.0001+00

.000B+00

.0001+00 1

.001 I

.00]

.000+00

.000.+00

.0008+00

.000E+00

.OOOE+00 I

.001 1

.001

.0003+00

.oooe+00

.0001400 ooe000 1

.001

.000R+00

.0008+00

.000E+00

.000B+00 FOR SCENARIO DURATION (7.20001+02 bra)

COMPARTMENT C (lnemispher) 7.3578+00 7.3711-02 2.0641+00 1 97.251 5.7171-02 8.2113-02 3.9401-01 1 89.411 6.1263-02 1.359e-01 9.132E+01 C 99.951 7.391Z-02 2.8461+00 C 90.391 1.326E+02 6.6423-02 OFFBITS RZCEP.

.0001z00

.0001+00

.0001+00 I

.001

.0001+00

.0003+00 I

.001

.0003+00

.000B+00

.0003+00 I

.001

.0008+00

.000+00 I

.001

.OOO+00

.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 AR EVA 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 ID 32-5052589-01 Page 64 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 COMPARTMENT C TOTAL RADIATION EXPOSURES (AIR IXMERSION PLUS INEALATION)

(PARTIAL OCCUPANCY)

Beta Air DOSE RATE T (hours)

(rad/hr)

.*0000+00 5.0000z-01 1.00003+00

2. 00003+00 8.00003+00 2.40003+.0

9. 60003+01 7.2000z+02

.0003400 6.122H400 3.3683.00 6.830B-01 2.908Z-02 2.670B-03 1.0543-04 1.127Z-06 Gonads DOSE RATE S (hours)

(rem/hr)

Beta Air INTVL DOS (rad)

.0003+00 2.*553300 2.3793+00 1.697E+00 5.873E-01 9.561B-02 4.1043-02 5.030B-03 Gonads NTVL DOS (rea)

.0003,00 1.880Z-02 1.751Z-02 1.285Z-02 6.2973-03 1.337Z-03 2.124B-04 9.4243-06 R.Karrow INTVL DOS (rem)

Beta Air CUM. DOSE (rad)

.0003.00 2.5533+00 4.932E+00 6.6283+00 7.2153+00 7.3113.00 7.3523,00 7.3573+00 Gonads CUM.

DOSE (rem)

.OOOZ300 1.880E-02 3.6313-02 4.916B-02 5.546B-02 5.6803-02 5.701B-02 5.7023-02 R.Marrow CUM.

DOSE (rem)

GOn-a Air DOSE RATE (rad/hr)

.OOO+00 5.693Z-02 3.163E-02 7.196B-03 6.612E-04 4.917Z-05 9.811B-07 1.591B-08 Breast DOSE RATE (rem/hr)

.0003+00 6.608Z-02 3.657Z-02 7.874E-03 5.186B-04 3.752E-0S 5.985E-07 7.142E-09 Bone Sur DOSE RATE (rem/hr)

Gamma Air INTVL DOS (rad)

.000E+00 2.382E-02 2.2183-02 1.642Z-02 8.6878-03

1. 9763-03 5.7283-04 5.7793-05 Breast rNTVL DOS (rem)

.0003+00 2.7603-02 2.5723-02 1.871E-02 8.0913-03 1.5373-03 2.4873-04 1.1978-05 Bono Sur rNTVL DOS (rem)

Gamna Air CUM.

DOSE (rad)

.0003+00 2.3823-02 4.600B-02 6.2413-02 7.1103-02 7.3083-02 7.3653-02 7.3713-02 Breast CBM. DOSE (rem)

. 000E.00 2.760E-02 5.3323-02 7.2043-02 8.0133-02 8.1663-02 8.191Z-02 8.1923-02 Bone Bur CUM.

DOSE (rem)

Tot. Skin DOSE RATE (rem/hr)

.000E+00 1.6883z00 9.2783-01 1.930B-01 1.136B-02 8.0690Z-04 1.939Z-05 2.493B-07 Lungs DOSE RATE (rem/hr)

.0003+00 3.4233-01 1.8843-01 3.620B-02

.4.408B-04

3. 104E-05 3.8943-07 3.167B-09 Thyroid DOSZ RATE (rem/hr)

Tot. Skin INTVL DOS (rem)

.0003+00 7.039B-01 6.S55B-01 4,697Z-0O 1.a85-01 3.5163-02 6.350-03 4.0358-04 Lungs INTVL DOS (rem)

.000B00 1.418z-01 1.3323-01 9.376B-02 2.356B-02 1.2943-03 1.9553-04 6.5473-06 Thyroid INtVL DOS (rem)

Tot. Skin CUM.

DOSE (re=)

.0003+00 7.039E-01 1.3593.00

1. 8293.00 2.0183+00 2.0533+00 2.0593+00 2.0593+00 Lungs CUM. DOSE (rem)

.OOO+00 1.418Z-01 2.751Z-01 3.688E-01 3.9243-01 3.9373-01 3.9393-01 3.939Z-0O Thyroid CVM.

DOSE (rem)

.00003+00 5.0000E-01 1.0 000E+00 2.00003+00 8.00003+00 2.40003+01 9.60003+01 7.20003+02

.0003+00 4.497E-02 2.492E-02 5.537B-03 4.521E-04 3.248E-05 4.9843-07 5.421-09 R.Marrow DOSE RATE T (hours)

(rem/hr)

.00003+00

5. 0000-0O1 1.0000E+00 2.00002+00 8.00003+00 2.40003+01 9.60003+01 7.20003+02

. 000+00 4.897B-02 2.711Z-02 5.900B-03

4. 1943-04 2.9203-05 3.238Z-07 2.693B-09

.0003+00 2.047Z-02 1.906B-02 1.391Z-02 6.2833-03 1.228Z-03 1.7913-04 5.482E-06

.0003+00 2.047P-02 3.953E-02 5.3443-02 5.9721-02 6.0953-02 6.1133-02 6.113E-02

.0003.00

1. 091B-01 6.032Z-02 1.300Z-02 8.8003-04 6.7343-05 1.440*-06 1.2573-08

.0003+00 4.557E-02 4.2443-02 3.087Z-02 1.350-02 2.6643-03 4.899E-04 2.508Z-05

.0003+00 4.557B-02 8.8013-02 1.189Z-01 1.3243-01 1.3503-01 1.355B-01 1.356E-01

.0003+00 8.0163+01 4.4113+01 8.4173+00 6.8213-04 3.2613-05 4.552B-07 4.639E-09

.0003+00 3.3383+01 3.1173+01 2.1953+01 4.8163+00 1.477B-03 2.097B-04

8. 435B-06

.0003+00 3.3383+01 6.4553+01 8.6503+01 9.1323+01 9.1323+02 9.1323+01 9.1323+01

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 ID 32-5052589-01 Page 65 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

COMPARTMENT C TOTAL RADIATION HIPOSURES (AIR IM1IRBION PLUS INXALATION)

(PARTIAL OCCUPANCY)

Remilndr DOSE RATE T (hourn)

(rem/hr)

. ooooe+00 5.0000R-01 1.00003+00 2.00001+00 8.0000X.00 2.40003+01 9.60001+01 7.20003+02

.000+.00 6.013B-02 3.329R-02 7.052R-03 4.200E-04 2.959R-05 3.698Z-07 3.215E-09 Re-aIndr INTVL DOS (rem)

.0003+00 2.503Z-02 2.3423-02 1.696R-02 6.934B-03 1.234R-03 1.86CR-04 6.387B-06 RGIXO9Wa INTYv DOS (rem)

.000X*00 2.1423-02 1.992B-02 1.4763-02 7.9583-03 1.8241-03 3.048B-04 1.322B-05 Remaindr CUM.

DOSE (rem)

.O000O00 2.5033-02 4.8453-02 6.541R-02 7.235B-02 7.358B-02 7.3773-02 7.377B-02 Bff D.E.

DOSE RATE (rem/hr)

.000x+OO 2.493+.00 1.372+.00 2.626R-01 4.6623-04 3.282E-05 4.6663-07 4*.615B-09 Zff D.E.

INTVL DOS (rem)

.0003.+00 1.0385+00 9.697Z-01 6.8333-01 1.533Z-01 1.360R-03 2.122B-04 8.5333-06 3ff D.E.

TID Thy CUM. DOSE DOSE RATE (rem)

(rem/hr)

.0001+OO

.0003+00 1.0383+00 1.1653+02 2.008B+00 6.4033+01 2.6913+00 1.2203+01 2.8443+00 3.225S-04 2.8461+00 1.998B-16 2.8463+00 2.6783-71 2.846E.00

.0001.00 TID Thy INTVL DOS (ram)

.0003.00 4.851+401 4.5273+01

3. 1841.01 6.966Z+00 1.8353-04 6.8271-17 6.107Z-72 TID Thy CUM. DOSE (rem)

.OOO+00 4.8513401 9.3783+01 1.2563+02 1.3261+02 1.3261+02 1.3261+02 1.3263.02 RTOG19WB DOSE RATE T (hours)

(rem/hr)

.00003+00 5.0000-01 1.00003+00 2.0000E+00 8.00003+00 2.40003+01 9.60003+01 7.2000E*02

.0003+00 5.114Z-02 2.8403-02 6.496Z-03 6.1281-04 4.4963-05 7.6153-07 6.641E-09 R01109WB CUM.

DOSE (rem)

.OOO+00 2.1423-02 4.1343-02 5.6103-02 6.405B-02 6.5883-02 6.6183-02 6.620Z-02

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Temm Methodology (2038 MWI)

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 I%)1 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 PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 A

Based on the Alternative Source Term Methodology (2038 MWI)

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

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 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)

NUCL.

GROUP CONPAMSMENT A FBCTRC.

COMPAR~mN B RZCIRC.

COMPARTMENT C RECIRC.

EXRAUST TO ATMOSPHERE INTAKE TO COMPART.

C 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 2

.0000 3

.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 1

KR XE 2

BR I

3 ZZ FORM 1

1. 000S00 2.850-03

.000Z+00 FORM 2

. 0003+00 2.150E-03

.0003+00 FORM 3

.OOO+00

.OOOE+00

.000oe00 ELEMENT ZZ' STANDS FOR THe REMAINING DATA-LIBRARY ELENENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

A PNPS Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Termn Methodology (2038 MWt)

A R E VAt Prepared by: John N. Hamawi Document ID 32-5052589-01 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 (bourn)

CONCENTR.

X/Q (sec/=3) 1.760-03 1.760Z-03 1.760Z-03 1.250B-03 GAMMA X/Q (sec/m3) 1.760B-03 1.7601-03 1.7601-03 1.250Z-03 DEPOSITION D/Q (1/=2)

.0001+00

.000B+00

.0001+00

.0001.00 BREATNnnG RATE (m3/sec) 3.5003-04 3.5001-04 3.500X-04 3.5001-04 EI.PFILT.

BYPASS FRACTION

.000R+00

,.OOOE+00

.0008+00

.OOOE+00 COMPART.

C IN?.FILTZR BYPASS FR.

.0001+00

. 0001+00

. OOO+.00 COMPART. C OCCUPANCY FACTOR 1.0001.00 1.0001+40 1.0001+00 1.000+00

.OOOOE00 5.0000B-01 1.0000X+00 2.00001E00 5.0000Z-01 1.00001.00 2.0000E+00 8.00001+00 8.0000+00 2.40001.01 9.60001+01 2.4000Z+01 9.60001+01 7.2000E+02 4.2601-04 3.670Z-04 3.15OE-04 4.2601-04 3.670B-04 3.1501-04

.000z+00

.0oooz00

.000x+00

3. 5001-04 3.5001-04 3.5001-04

.0001+00

.00o0+00

.0001.00

.0001+00

.000oo00

.0001+00 1.0001.00 6 *0001-01

4. 0001-01 TIME INTERVAL (hours)

COMPART A

MULTIPLIERS (IF APPLICABLE)

LEAK RATE

, REC.PILTZR COMPART B MULTIPLIERS (IF APPLICABLE)

LEMA RATE REC.FILTzR COMPART C

MULTIPLIERS (Ir APPLICABLE)

INTPA 4 E/IX RXC.FILTER FLOW MULT.

SPRAYED AREA TO UNSPRAYED

.000o0+00 5.00001-01 1.0000+.00 2.00001+00

.o0000z+00 2.40001+01 9.66000+01 5.0000Eo-0 1.0000Z+00 2.0000H+00 8.0000E+00 2.40001+01 9.60001.01 7.2000Z+02 1.0001+00 1.0001+00 1.000E+00 1.000z+00

1. 000+00 1.0001+00 1.000E+00 1.000o+00

1. 0001E00

1. 0001+00 1.0001+00

1. 0001.00

1. 0001+00

1. 000+00

1. 0001+00 1.0001+00 1.0001+00 1.0001+00 1.000o+00 1.0001+00

1. 0001+00 1.0001+00

1. 0001+00 1.000R+00

1. 000Z+00 1.0001+00 1.0001+00

1. 000+00 1.*000+00 1.0001+00 1.0001+00 1.0001+00

1. 000100 1.000B+00 1.000X+00

1. 000+00

1. 0001Z00

1. 0001+00

1. 000+E00 1.0001+00 1 *000Z+00 1.000Z+00 1.000Z+00 1.0001+00

1. 000+00

1. 000+00 1 000E+00 1.0001+00

1. 0001+00

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 ID 32-5052589-01 Page 70 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 USER-SPECIFIED SOURCE INVENTORY (INSTANTANEOUS RELEASE FROM SOURCE)

NUCLIDE BR 82M BR 82 BR 83 BR 84M BR 84 BR 05 BR 86 BR 87 BR 88 KR 83M KR 85M KR 85 GROUP 2

2 2

I 1

I.

(CL) 7.89203+01 2.04203+02 2.5670E+03 1.3280E+02 4.7330z+03 5.8150R+03 4.35603+03 9.92103+03 1.13003404 2.56703+03 5.88003+03 8.5510E+02 NUCLIDE KR 87 KR s8 FR 89 KR 90 1128 1129 1130M I130 X131 X132 X133 11343 GROUP 1

1 1

1 2

2 2

2 (Ci)

1. 1750E+04 1.66203+04 2.09603+04 2.08103+04 5.70203+02 1.7930K-03 5.40203+02 1.38303+03 2.7170R+04 2.41103+04 3.4170R+04 4.07403.03 NUCLIDE 1134 1135 1136H.

1136 XZ131M XR133M XE133 XE135M XZ135 Xe137 XE138 XZ139 GROUP 2

2 2

2 1

1 1

1 I

I 2.2 May (Ci) 3.81503+04 3.18203+04 9.44603+03 1.54403+04 1.90503+02 1.05203+03 3.41703+04 6.82503+03 1.74403+04 3.00703+04 3.03703+04 2.4470E+04 23,20021 28-Oct-04 PAGE 31 EL$SA-2 (LICENSING & SEVERE ACCIDENT RADIOLOGICAL EVALUATIONS -

ENTEC ENm.

Rol. Version CASE# 2 PNPS AST -

MMA -

BOUNDING 5RC -

24 RR DECAY -

RB VENT RELBASES -

CR -

9000 CFH (INSTANTANEOUS RELEASE FROM SOURCE)

SOURCE NUCLIDB BR 82 BR 83 BR 84 KR 83M KR 85M FR 85 RR 87 KR 88 RB 87 RB 88 RB 89 INVENTORY FOLLOWING GROUP (C1) 2 1.27613+02 2

2.43523+00 2

1.1057B-10 1

9.44453+00 1

1.45053+02 1

8.55013+02 1

2.47292-02 1

4.74433+01 3

3.6297R-11 3

5.2925E+01 3

1.6731E-25 2.4003+01 fOURS NUCLIDR SR 09 1128 1129 S130M 1130 1131 1132 1133 1134 1135 S8131M OF RADIOACTIVE GROWMT AND DECAY PRIOR TO RELEASE GROUP (CL)

NUCLIDE GROUP (CL) 3 9.0150Z-01 X1333M 1

9.4669+.02 2

2.54193-15 X3133 1

3.28693+04 2

1.79303-03 X3135M 1

4.11603+02 2

3.69633-46 X3135 1

9.60503+03 2

3.61473+02 X8138 1

7.77763-27 2

2.49263.04 C8135 3

6.6014E-06 2

1.74193+01 CS137 3

7.29873-03 2

1.53573+04 C8138 3

8.23373-10 2

.2.18963-04 CS139 3

1.41353-43 2

2.5697E+03 BA137M 3

6.9045X-03 1

1.96063+02 BA139 3

1.27003-03

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

A R EVA Prepared by: John N. Hamawi Document ID 32.5052589-01 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.

NUCLIDE COMPARTM.

A (CL/m3)

HR 82 3.219Z-05 8R 83 6.143Z-07 8R 84 2.789Z-17 KR 83N 4.765E-04 KR 85M 7.3188-03 KR 85 4.314Z-02 KR 87 1.248Z-06 KR a8 2.3943-03 1128 6.412E-22 1129 4.523E-10 1130M 9.324E-53 1130 9.118E-05 1131 6.288B-03 1132 4.3943-06 1133 3.874E-03 X134 5.523B-11 1135 6.4823-04 XZ131M 9.891Z-03 XE133M 4.776Z-02 XE133 1.6583+00 XZ135M 2.077Z-02 XE135 4.846x-Ol X3138 3.924E-31 DISTRIBUTION OF CREM-SPRAY IN COMP. A (CL)

.OOO+00

.0003.00

.0003+00

.OOO+00

.OOO+OO

.000z+00

.000+00

.*000+00

.0003.00

.OOO+00

.000+00

.0003+00

.000+00

.0003+00

.000+00

. 000+00

.000+00

.0003+00

.000+00

.0003+00

.000+00

.0003+00

.OOO+00 REC.7FLTER IN COMP. A (Ci)

.OOOZ+00

.OOO+00

.0003+00

.OOOE+00

.0003+00

. 000X+00

.0003+00

.000+00

.0003+00

.0008+00

.0003400

.0003+00

.000+00

.OOO+00

.0003+00

.OOO+00 COMPARTH.

B (ci/=3)

.0003+00

.OOO+00

.0003+00

.000E+00

.OOO+OO

.0005+00

.0003+00

.0003400

. 000+00

.OOO+00

.000+00

.0003+00

.000+00

.000Z+00

. 000+00

.0003+00

.000+00

.OOO+00

.000+00

.OOOR+00

.OOO+00

.0003+00

.OOO+00

.OOO+00 RADIOACTIVITY REC.FILTER IN COMP. B (Ci)

.OOO+00

.0003+00

.0005400

.0003+00

.OOO+00

.0005+00

.0003+00

.OOO+00

.0003+00

.0005+00

.0003+oo

.0003+00

.oooe+00

.0003+00

.0003+00 3X2.PILTER TO ATMOSU.

(Ci)

.0003+00

.000+00

.000Z+00

.0003+00

.OOO+00

.0003+00.

.OOO+00

.0003+00

.000+00

.0003+00

.000Z+00

.0003+00

.OOO+OO

.0003+00

.000+00

.0003+00

.OOO+.00

.oooE+6O

.000+00 COMPARTM.

C (Ci/=3)

.000+00

.OOO+00

.0003+00

.000E+00

.000+00

.0003+00

.000Z+00

.0003+00

.OOO+00

.0003+00

.000+00

.0003+00

.0003+00 INT.FILTZR TO COMP.

C (Ci)

.0003+00

.0ooo+00

.0003+00

.OOO+OO

. 000z+00

.0003+00

. 000X+00

.000+00

.0003+00

.0005+00

.0003+00

.000+00

.0003+OO

.0003+00

.000+00

.0003+00

.00O+00

.0003+00

.0003+00 REC.FILTSR IN COMP. C (CI)

.0003+00

.0005+00

.0003+00

.ooo0+oo OOO.+00

.0003+00

.000+00

.0ooo+00

.000+00

.0003+00

.OOO+00

.0003+00

.000+00

.0003+00

.Ooo0+00

.000+00

.0003+00 TOTALS GROUP 1

GROUP 2

GROUP 3 GRND. TOT 2.2753+00 1.0943-02

. 0003+00 2.2853+00 THE COMPARTMENT VOLUMES (A. H AND C) IN THIS TABLE ARE2 1.982E*04

.0009+00 9.707E+02 (m3)

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

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 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 NUCLIDZ BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 KR 87 KR 88 1128 1129 1130M 1130 1131 1132 1133 1134 1135 XE131M XZ133K X%133 XZ135M XR135 XZ133 TOTALS GROUP I

GROUP 2

GROUP 3

GPND.TOT WITHOUT DECAY IN TRANSIT REL. RATE XNTRV REL CUML. REL CLOUD CONC (Ci/hr)

(CL)

(Ci/r3) 2.5523+00

.000+00

.0003+00 1.248b-06 4.870s-02

.000Z400

.000X+00 2.381Z-08 2.211R-12

.000Z100

.0001.00 1.01l-18 3.7789+01

.000S+00

.0001.00 1.847B-05 5.8028+02

.0003+00

.0001+00 2.8371-04 3.420Z+03

.0008+00

.0003+00 1.672B-03 9.892B-02

.000Z400

.000Zt00 4.836Z-08 1.898Z+02 000.+00

.000Z+00 9.278Z-05 5.0843-17

.000Z+00

.0003+00 2.485B-23 3.586Z-05

.0001+00

.0001+00 1.753Z-11 7.393Z-48

.000B+00

.0001400 3.614E-54 7.229B+00

.OOOR+00

.000Z400 3.5341-06 4.9851+02

.0001+00

.0003+00 2.4373-04 3.4841-01

.000Z+00

.0001.00 1.703R-07 3.071Z+02

.000.+00

.0003+00 1.502Z-04 4.379Z-06

.000Z+00

.0001+00 2.1411-12 5.1391.01

.00O0100

.000.+00 2.513Z-05 7.8438+02

.0001+00

.000B+00 3.834Z-04 3.787E+03

.0001+00

.000Z+00 1.851Z-03 1.315Z+05

.0001400

.0001400 6.4283-02 1.6463+03

.0003+00

.0003400 8.049Z-04 3.842E+04

.0001+00

.000.+00 1.878Z-02 3.1118-26

.000+00

.0001+00 1.521B-32 INTRv REL (Ci)

.0001.00

.0001400

.O0001.00 OOO+00

.0001400

.OOO+400

.0001400

.0003+00

.000Z.00

.0003.00

.000Z+00

.0001400

.0001.00

.0003400

.0001.00

.0003.00

.0001C+00

.0003400

.0003+00

.0001+00

.0OOO+OO

.0001+00

.000z+00 CUML.

REL (Ci)

.0001+00

.0OOO+00

.0003.00

. 000Z+00

.000+00

.0003+00

.0001.00

. OOOZ+00

.0003+00

. OOOZ+OO

.0003+00

0001.00

.0OOO300

.0OOO+00

.0003+00

.0001+00

.000Z+00

.000B+00

.0001+00

.0OOO+00

.000.+00

.0001+00

.000+00

.0003400 CLOUD CONC (Ci/m3) 1.2483-06 2.381Z-08 1.031E-18 1.847E-05 2.8373-04 1.6721-03 4.8361-08 9.278B-05 2.4851-23 1.7531-11 3.6141-54

3. 534-06 2.4373-04 1.703Z-07 1.5021-04 2.1413-12 2.5133-05 3.8341-04 1.851Z-03 6.4289-02 8.0493-04 1.8783-02 1.521Z-32 8.817B-02 4.2401-04

.000Z+Oo 8.859Z-02 WITH

.0001+00 hre IN-TRANSIT DECAY 1.803Z+05 8.6721.02

.0008+00 1.8121+05

.0003+OO

.000+00

.000R+00

.000o+00

.0001o00

.0001+00

.0ooo000

.OOOE+00 8.8178-02 4.240Z-04

.0008+00 8.8593-02 1.803Z+05 8.6721+02

.000,+00 1.812E+05 NOTZE THE ATMOSPHERIC CONCENTRATION OF RADIOACTrVITY I8 BASED ON A DISPERSION FACTOR (X/Q)

OF 1.7603-03 (foclm3)

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

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 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 COMPARTMWNT C TOTAL RADIATION zXPOSURES (AIR IMMERSION PLUS INHALATION)

(CONTINUOUS OCCUPANCY)

Beta Air DOSE RATE T (hours)

(rad/hr)

.00004E00 5.00008-01 1.00001400

2. *0000100 8.0000e+00 2.4000Z+01 9.60001+01 7.20001.02

.000E+00 5.1161+00 7.681Z-01 1.008B-01 3.5711-02 3.082E-03 1.043B-04 1.126E-06 Gonads DOSE RATE T (hours)

(rem/hr)

. 0000Z+OO 5.0000E-01 1.00001.00 2.0000Z+00 8.00001+00 2.4000.+01

9. 6000e+01 7.2000E+02

.000H+00 3.867Z-02 7.108B-03 2.153Z-03 7.9241-04 5.410E-05 4.9241-07 5.418B-09 Beta Air INTVL DOS (rad)

.OOOZ+00 5.757Z+00 1.131Z+00 2.566E-01 2.9211-01 1.052Z-01 4.4011-02 4.9901-03 Gonads INTVL DOS (rem)

.0001o+00 4.2741-02 8.9701-03 3.350B-03 6.624Z-03 2.166Z-03 5.293B-04 2.3451-05 R.Marrow INTVL DOS (ram)

.000+00 4*6461-02

9. 6341-03 3.3391-03 6.240B-03 2.0241-03 4.667E-04 1.366B-05 Beta Air CUM.

DOSE (rad)

.000e+00 S.7571+00 6.888Z+00 1.1441+00 7.436E+00 7.5411.00

7. 585E+00 7.5901+00 Gonads CUM. DOSE (rem)

.0001+00 4.2741-02 5.171E-02 5.5061-02 6.169z-02 6.385Z-02 6.438Z-02 6.441E-02 R.Narrow COU.

DOSO (rem)

.0001+00 4.6461-02 5.6098-02 5.9438-02 6.5673-02 6.7701-02 6.816S-02 6.8181-02 Gamma Air DOSE RATE (rad/hr)

.000B+00 4.9231-02 9.3871-03 3.103Z-03 1.1521-03 8.033E-05 9.843X-07 1.590Z-08 Breast DOSE RATE (rem/hr)

.0001+00 5.633Z-02 9.770Z-03 2.4961-03 9.0821-04 6.2271-05 6.027Z-07 7.1371-09 Bone Sur DOSE RATE (rem/hr)

.000X+00 9.287E-02 1.600Z-02 4.021Z-03 1.4721-03 1.0499-04 1.44 0-06 1.2571-08 Gamma Air IN5SL DOS (red)

.0001.00 5.422E-02 1.1531-02 4*6301-03

9. 605-03 3.168E-03 8.2471-04 5.753Z-05 Breast INTVL DOS (rem)

.000E+00 6.260Z-02 1.2881-02 4.2361-03 7.59SE-03 2.486B-03 6.1501-04 2.977B-05 Bone Sur INTVL DOS (rem)

.000o+00 1.033B-01 2.119B-02 6.883Z-03 1.226Z-02 4.0741-03 1.118B-03 6.1225-05

¢Game Air CUn.

DOSE (red)

.000Z00 5.422Z-02 6.5751-02 7.0381-02 7.999E-02 8.3161-02 8.3981-02 8.404Z-02 Breast CUM.

DOSE (rem)

.OOO+00 6.260Z-02 7.5481-02 7.972Z-02 8.731E-02 8.980Z-02 9.0411-02 9.044Z-02 Bone Sur CUM.

DOSE (rem)

.000H+00 1.0331-01 1.245Z-01 1.314E-01 1.437B-01 1.4781-01 1.489z-01 1.4891-01 Tot. Skin DOSE RATE (rom/hr)

.000E+00 1.420B+00 2.2491-01 4*127Z-02

.1.4781-02 1 085E-03 1.9261-05

2. 492B-07 Lungs DOSE RATE (rem/hr)

.000B+00

.2.8421-01 4.028E-02 2.7121-03 7.7721-04 5.247B-05 3.9441-07 3.1661-09 Thyroid DOSE RATE (rem/hr)

.0001+00

.6.622Z+01 8 *9591+00 1.6511-01 8.0481-04 5.467E-05 4.598B-07 4.636E-09 Tot. Skin INTlY DOS (rem)

.000+00 1.590E+00 3.175Z-01 8.4441-02 1.230E-01 4.1328-02 1.227B-02 1.0021-03 Lungs INTVL DOS (rem)

.0001+00 3.185B-01 6.2131-02 1.142z-02 6.620B-03 2.117B-03 4.9981-04 1.629Z-05 Thyroid INTVL DOS (rem)

.0001+00 7.5071+01 1.4331+01 2.1971+00 3.8608-02 2.1978-03 5.285E-04 2.099E-05 Tot. Skin CDM.

DOSE (rem)

.0001+00

1. 5901+00 1.9071+00 1.9921+00

2. 115E+00 2.1561+00

2. *168+00 2.1691+00 Lungs CUM. DOSE (rem)

.000B+00 3.185Z-01 3.8078-01 3.92I1-01 3.987Z-01 4.008Z-01 4.013Z-01 4.0131-01 Thyroid CUM.

DOSE (rem)

.0001+00 7.507Z+01 8.9391+01 9.159z+01 9.163Z+01 9.1631+01 9.1631+01 9.163E+01 R.Marrow DOSE RATE T (hours)

(rem/hr)

.00001+00 5.00001-01 1.00001+00 2.0000Z100 8.00001+00 2.40001+01 9.6000x+01 7.20001+02

.0001+00 4.1903-02 7.4381-03 2.0443-03 7.448B-04 4.989Z-0S 3.293Z-07 2.691E-09

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

A R E VA Prepared by, John N. Hamawi Document ID 32*5052589-01 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 COMPARTMENT C TOTAL RADIATION EXPOSURES (AIR 1MMBRS1ON PLUS INHALATION)

(CONTINUOUS OCCUPANCY)

Remaindr DOSE RATE T (hours)

(rem/hr)

. 0000E.00 5.0000e-0l 1.00005e00 2.00003+00 8.0000z+00 2.4000E+01 9. 6000S.01 7.20002+02

.000e+00 5.110o-02 8.6823-03 2.056R-03 7.41SE-04

5. 0S0-05 3.7463-07 3.213E-09 Remaindr 1NTVL DOS (rem)

.0003+00 S.663E-02 1.1633-02 3.6353-03 6.2153-03

2. 0213-03 4.7623-04 1.5903-Os R01109WB rNTVL DOS (rem)

.000E+00 4.881l-02 1.0403-02 4.2533-03

8. 9203-03 2.9333-03 7.4243-04 3.286z-05 Remaindr CUM.

DOSE (rem)

.0003+00

5. 6633-02

6. 263-02 7.1893-02 7.8118-02 8.0133-02 8.061B-02 9

00628-02 3ff D.E.

DOSE RATE (rem/hr)

.0003+00 2.06le+00 2.8071-01 7.168R-03 8.065s-04 5.4883-05 4.7103-07 4.6123-09 Bff D.e.

INTVM DOS (ram)

.0003+00 2.3353.00 4.4663-01 7.043Z-02 7.717E-03 2.202E-03

5. 3253-04

2. 123Z-05 3ff D.3.

CUM. DOSE (rem)

.0003+00 2.3353+00 2.7823+00 2.852R+00 2.8603+OO 2.862X+00 2.8633+00 2.8633+00 TSD Thy DOSE RATE (rem/hr)

.0003.00 9.620E+01

-1.3003+01 2.362B-01 6.0433-12

2. 9743-40

.0003+00

.0003+00 TID Thy INTVL DOS (rem)

. 000o00 1.0913+02 2.0813+01

3. 1853+00 4.6193-02 7.6673-13 6.6563-41

.0003.00 TID Thy CUN.

DOSE (rem)

.0003+00 1.0913+02 1.299E+02 1.3313+02 1.3323+02 1.332Z+02 1.3323+02 1.3323.02 R011093B DOSE RATE T (hours)

(rem/hr)

.OOOO+00 5.00003-01

1. *000000 2.00003+00 8.00003+00 2.4000Z301

9. 6000z+01 7.20003+02

.0003.00 4* 430-02 8.5213-03 2.879e-03 1.0693-03 7.3923-05 7.6533-07 6.6373-09 RGl0l9WB CUM.

DOSE (re=)

.0001t+00

4. 8813-02

s. 921E-02 6.34 6-02 7.2383-02 7.5313-02

7. 606-02 7.6093-02

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32.5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

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 AR 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 ID 32-5052589-01 Page 76 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 COZIPARTHENT C TOTAL RADIATION EXPOSURES (AIR rNMERSION PLUS SNiATION)

(PARTIAL OCCUPANCY)

Beta Air DOSE RATE T (hourn)

(rad/hr)

. 0000Z00 5.0000e-01 1.OOOOE+00 2.00001+00 8.0000Z00 2.4000B+01 9.60001+01 7.2000E+02

.0001+00 5.1161.00 7.681B-01 1.008Z-01 3.571B-02 3.082Z-03 1.0431-04 1.126B-06 Beta Air 1tTrvr DOS (rad)

.000+.00 5.757N+OO 1.131Z+00 2.5661-01 2.921B-01

1. 052z-01

4. 4012-02 4*990Z-03 Gonads lNTVL DOS (rem)

.000H+00 4.2741-02 8.970B-03 3.3501-03 6.6241-03 2.166Z-03 3.1761-04 9.3801-06 Beta Air CUM.

DOSE (rod)

.0001+00 5.757E100 6.888E+00 7.1441400 7.4361+00 7.541X+00 7.5851+00 7.5901+00 Gonads CUM.

DOSE (rem)

.OOO+00 4.2741-02 5.171B-02 5.5061-02 6 1691-02 6.381E-02 6.417E-02 6.4181-02 Gazm Air DOSE RATE (rad/br)

.0001+00 4.9231-02 9.387Z-03 3.1038-03 1.152E-03 8.0331-05 9.8431-07

1. 590-08 Breast DOSE RATE (rem/hr)

.0001+00 5.633Z-02 9.770Z-03 2.4961-03 9.0821-04 6.227B-05 6.027B-07 7.137Z-09 Ga=a Air INTVL DOS (rod)

.000B+00 5.422Z-02 1.153Z-02

4. 630e-03 9.6058-03 3.168Z-03 8.247E-04 5.7531-05 Breast flTVL DOS (rem)

.0001+00 6.2601-02 1.2881-02 4.236Z-03 7.5958-03 2.4861-03 3.6901-04

1. 191-05 Gamma Air CUM. DOUR (rad)

.0001+00 5.4221-02 6.5751-02 7.0351-02 7.999Z-02 8.3161-02 8.398Z-02 8.4041-02 Breast CUtM.

DOSE (rem)

.0001+00 6.260Z-02 7.5481-02 7.9721-02 8.7311-02 8.980Z-02 9.017Z-02 9.018B-02 Tot.

Skin DOSS RATE (rem/hr)

.0001.00

1. 420Z+00 2.2491-01 4.127Z-02 1.4781-02

1. 085-03 1.926Z-05 2.4921-07 Lunge DOSE RATS (rem/hr)

.0001.00 2.8421-01 4.0281-02 2.7122-03 7.772B-04 5.2471-05 3.9441-07 3.166Z-09 Tot. Skin INTVL DOS (rem)

.0001+00 1.590z+00 3.175Z-01 8.4441-02

1. 2301-01 4.1321-02 7.360Z-03 4.o008-04 Lungs INTVL DOS (rem)

.OOO+00 3.1851-01 6.213Z-02 1.1421-02 6.6201-03 2.1171-03

2. 999s-04

6. 517-06 Tot. Skin CUM. DOSE (rem)

.000E+00 1.590E+00 1.9071+00 1.9921+00 2.1151+00 2.1s6z+00 2.163E+00 2.1641+00 Lungs CUM.

DOSE (rem)

.0001+00 3.185Z-01 3.807E-01 3.9211-01 3.9871-01 4.008Z-Ol 4.011Z-01

4. 011Z-Ol Gonads DOSE RATE S (hours)

(rem/hr)

.00001+00 5.00001-01

1. 0000E+00 2.0000Z+00

8. 00001+00

2. 40001+01 9.60001+01 7.2000E+02

.0001+00

3. 867z-02 7.108Z-03

2. 1531-03 7.9241-04

5. 410*-05

4. 924E-07 5.4181-09 R.Marrow DOS RATE T (bourn)

(rem/hr)

.00001+00

5. 0000101 1.00001+00 2.00001+00 8.0000Z+00

2. 4000+01 9.60001+01 7.20001+02

.000E+00 4.1901-02 7.4381-03 2.044B-03 7.448R-04 4.9891-05 3.2938-07 2.691E-09 R.Narrow INTVL DOS (rem)

.0001+00 4.646Z-02 9.6341-03 3.339s-03 6.240B-03 2.0241-03 2.8003-04 5.4621-06 R.Marrow CUM.

DOSE (rem)

.0001+00

4. 646E-02 5.6091-02 5.943X-02 6.567N-02 6.7701-02 6.7991-02 6.798E-02 Bone Sur DOSE RAT!

(rem/hr)

.0003+00

9. 2871-02 1.600B-02 4.0211-03 1.4721-03 1.0491-04

1. 440-06 1.257z-08 Bone Our rNTVL DOS (rem)

.000+00 1.033Z-01 2.119Z-02 6.8831-03 1.2261-02 4.074E-03 6.7111-04 2.4901-05 Bone Sur CVM. DOSE (rem)

.0001.00 1.0331-01 1.2451-01 1.3141-01 1.4371-01 1.4781-01

1. 4841-01 1.4ss8-01 Thyroid DOSE RATE (rem/br)

. 0001+00 6.6221+01 8.9s9sz00 1.6511-O0 8.048B-04 5.4671-OS 4.5981-07

.4.636z-09 Thyroid INTVL DOS (rem)

.000Z+00 7.5071+01 1.4331+01 2.1971+00

3. 860z-02 2.1973-03 3.171B-04 8.396z-06 Thyroid CUM. DOSE (rem)

.000o+00 7.5071+01

8. 9391+01 9.159Z+01 9.1631+01 9.1631+01 9.1631+01 9.163E+02

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 ID 32-5052589-01 Page 77 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 COMPARTMENT C TOTAL RADIATION EXPOSURES (AIR nl9MRSION PLUS nMALATION)

(PARTIAL OCCUPANCY)

Remalndr DOSE RATE T.(hours)

(rem/hr)

.0000Z+00 5.00001-02 1.0oooo00 00 2.00001+00 8.00001+00 2.4000B+01 9.6000H401 7.2000B+02

.000o+00 5.210Z-02 8.6821-03 2.056E-03 7.4128-04 5.0051-05 3.746E-07 3.213B-09 Rmaindr INTVL DOS (rem)

.000R+00 5.663l-02 1.163Z-02 3.635e-03 6.21SB-03 2.021B:03 2.8571-04 6.359s-06 R51109wB SNTVL DOS (rem)

.OOO+00 4.8811-02 1.0401-02 4.2531-03 8.9201-03 2.933E-03 4.454R-04 1.3141-05 Renaindr CUM. DOSE (rem)

.0001+00 5.6631-02 6.8261-02 7.189Z-02

7. 811-02

8. 0131-02 8.0421-02 8.042U-02 Bff D.E.

DOSE RATE (rem/br)

.0oooe00 2.061e+00 2.807E-01 7.1681-03 8.06s5-04 5.4881-05 4.7101-07 4.6121-09 Zff D.E.

INTVr DOS (rem)

.000B+00 2.33s5+00 4.4661-01 7.0431-02 7.7171-03 2.202Z-03 3.19SE-04 8.4931-06 1ff D.C.

CUM. DOSE (re )

.0001+00 2.3351+00 2.7821+00 2.8521+00 2.8601+00 2.8621+00 2.8631+00 2 8631+00 TID Thy DOSE RATE (rem/hr)

.000K+00 9.620E+01 1.3001+01 2.362E-01 6.0431-12 2.9741-40

.0001+00

.000R+00 TID Thy INrVL DOS (rem)

.0001+00 1.0911+02 2.081R+01 3.1851+00 4*.619B-02 7.667B-13 3.9941-41

.0001+00 TID Thy CUM.

DOSE (ren)

.0008+00 1.0911+02 1.2991+02 1.3311+02 1.3328+02 1.3321+02 1.332Z+02 1.332E+02 RO11O9WB DOSE RATE T (hourn)

(rem/hr)

.0000E+00

5. 0000-01 1.ooooe+00 2.ooooe+00 9.00001.00 2.40001+01

9. 60001+01 7.2000E+02

.000R+00 4.4305-02 8.5211-03 2.8793-03 1.0691-03 7.392z-05

7. 63E-07 6.637e-09 RG1109WB CUM. DOSs (rem)

.oooe+00 4.8811-02 5.9211-02 6.3461-02 7.238E-02 7.531B-02 7.5766-02 7.577E-02

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32*5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

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 MND OF THIS CASE

- ^*******

END OF ANALYSrs

A AR 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 ID 32-5052589O1 Page 79 ELISA-2 Run Case #B - Main Output File

A AR EVA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MW!)

Prepared by: John N. Hamawi Page 80 oauaoee of##"##

8 a,.

a 4##I

9 a§ 8

8 99#

t 08 ooaou#

Ia O8Ifl88 O

t t

t a

t 60 t

8 a

a a

to###

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 DATA LIBRARY FLE......

s OUTPUT TILE...........

s PBOTON SPECTRA FILE 81 t PBOTON SPECTRA FILE *2 :

liga2-FHA-AS.e11

/SCL/oe11a2-2.2/eliaa2-2.1lb eliga2-PEA-A..12 oeita2-FIZA-XA".e13 e1Lsa2-FIIA-zAB.o14

A AREVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32*5052589-01 Based on the Atternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hramawi Page 81 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

10003 4

10004 5

1 6

2 7

3 8

10006 9

BR82 10 BR84M 11 BR88 12 X128 13 1131 14 X134K 15 1283K 16 1288 17 XE131M 18 XB135M 19 10007 20 10010 21 0.0 22 10018 23 0.0 24 10019 25 0.0 26 10021 27 0.0 28 99999 3

6 8

1 0

0 1.0 24.0 0.0 0.0 YrYYYy 3

0 1.000Z+00 2.850B-03 0.000z+00

-1.0001+00 2.042z+02 1.3292+02 1.1302+04 5.7021.02 2.7171+04 4*0742.03 2.567S+03 1.6621.04 1.905E+02 6.825C.03 2 7.02+05 4

0.5 1

7.4791-04 1

3.199Z-04 1

3.52-04 0

.0OOE+00

.0002.00 2.150Z-03

.0003+00

.000H+00.OOO+00 KR XE BR I zz

.0002400 BR82M 7'

DR85 S

1129 1.

1132 2

1135 3.

KR85 8.

KR89 2

X2133 3

XZ137 3

96.0 1

.8922+01 BR83

.815R+03 BR86 2.5671.03 BR84 4.3561+03 BR87

.793Z-03

.4112.04

.1822+04

.5511.02

.0962+04

.417E.04

.0072+04 0.0 1130 1133 1136 XR85M XR90 XE133M Xz138 0.0 1.3831+03 3.4172.04 1.5442+04 5.8801.03 2.0812.04 1.0521+03 3.0371.04 0.0 1130K 1134 1136M KR87 X8135 XZ139 0.0 4.7332+03 9.9212.03 5.402z202 3.8152.04 9.4462+03 1.1752+04.

1.744E+04.

2.447+.04 Refueling Level' 1.0 2.0

A AREVA 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 ID 32-5052589-01 Page 82 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 3

REMARKS (START)

V2L1 4

Source inventories are in Ci for the power level specified for each plant.

V2LI S

Decay constants are in inverse hours.

V2Ll 6

The entry line following the decay chains includes the decay constants V2L1 7

for each of three members [parent (P),

daugher (D) and granddaughter V2Ll 8

(M)I, and the branching fractions (P-D),

(D-G) and (P-).

V2LI 9

Air Imersion DCrs are in (((Bv or Gy))/s)/(Bq/m3)], for semi-infinite cloud V2Ll 10 around-shine DCFs are in [((Sy or Oy))/s)/(Bq/m2)3 (surface contamination). V2Ll 11 Inhalation DCrs are In (gv/Bq)].

V2Ll 12 The inhalation DCF's are for the Lung Cleirance Class which yields the V2L1 13 highest Effective Dose Equivalent (1ff D.Z.)s the class is identified.

V2L1 14 Negative DC? entries imply data not available'.

V2Ll 15 ORGAN STID Thy Thyroid inhalation based on TID-14844 -

Iodine. only.

V2L1 16 ORGAN RG1109WB' W hole body gama dose using the Reg. Guide 1.109 DCFs.

V2L1 17 Skin DCFs are included along with the organ DCF9, but skin is not V2L1 18 considered as an organ.

V2L1 19 6/28/2004 V2L2 20 Added beta NeV/dis for BROS,

KR89, XR90, RM90M, R890, 1136, Xel37 & C9-139 V2L2 21 (Based on Kocher, DOB/TIC-11026, Radioactive Decay Data Tables (1981)

V2L2 22 READ FORMATS FOR THE RADIONUCLIDE DATA BASE V2L1 23 Line 1

Nuclide name and source inventories (4x,a6,10x,4e12.3)

V2L1 24 (Note:

Nuclide sequence No.

is not used)

V2L1 25 Line 2

header (a80)

V2L1 26 Line 3

Decay chain (3 members)

(9x,3(a6,6x))

V2Ll 27 Line 4

Decay constants & branching fractions (Ox,6e12.3)

V2Ll 28 Line 5

Header (aBO)

V2L1 29 Lines 6-9 18 ORIGEN-2 photons and I ICRP-38 beta (8x,6e12.3)

V2L1 30 Line 10 Header (a80)

V2Ll 31 Lines 11-16 Doae conversion factors (8x,6el2.3)

V2LI 1

3 4

5 6

7 8

9 10 11 12 13 14 is 16 17 18 2

3 4

19 20 21 22 23 24 25 26 27 28 32 END REMARKS V2Ll 29 33 34 35 36 37 38 39 40 41 42 43 44 45 GENZRAL DATA BASE V2LI 10

[ORGAN NAMES -

READ FORMAT (11x,6(a8,4x))j V2L1 Gonads Breast Lungs R.Mharrow Bone Our Thyroid V2Ll Remaindr 1ff D.E.

TID Thy R011091B (Skin)

V2L1 4

(Pow r plants and power levels (MWt)

- READ FORMAT (llx,&20,1x,e12.3) V2Ll PWR (33 GWD/MT 3.2%)

1.000+00 V21 PWR (50 (WDMIT 4.2%)

1.000+00 V2L1 BWR (27.5 GWD/MT 3%)

1.0001+00 V2L1 BWR (40 GWD/M?

3.4%)

1.000R+00 V2L1 18 (ORIGEN-2 upper limit energy in each gamma group (MeV) (8x,6e12.3)3 V2L1 2.000Z-02 3.0008-02 4.5001-02 7.0008-02 1.00OZ-01 1.5008-01 V2L1 3.0001-01 4.5001-01 7.00O

-01 1.000R+00 1.500Z+00 2.000X+00 V2L 2.500E+00 3.0008+00 4.0001+00 6.0001+00 8.0001+00 1.1001+01 V2L1 30 31 32 33 3'

35 36 37 3,

39 40 41 42

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWI)

A R EVA Prepared by: John N. Hamawi Document ID 32*5052589-01 Page 83 46 47

8 3

Factors to convert data library DCFr to proper units, as shown 1.0 Convert air riaeron DCF to [j((v or Oy)/l)/(Dq/n3)I 1.0 Convert ground shine DCX to [((Bv or ay)/I)/(Bq/m2)I V2LI V2L1 V2L1 43 4'

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 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 1.0 18 Air gaa 6.676B-16 1.502B-14 1.5023-13 18 Air gaa 1.829E-16 2.760B-16 2.325E-15 18 skin gas-1.138B-16 1.239E-14 1.317e-13 RADIONUCLIDE DATA BAJ 1

H 3

(Src Ci)

Decay chain, 3

6.403203-06 ORIGXN-2 18-

.0003400

,0003+00

.0003400 5.600R-03 Convert inhalation DCF to (SyIBql V2L1 DCF for sei-infinite monoener. cloud arc [(Gy/s)/(Bq/m3)3 V2L1 1.6693-15 2.5033-15 3.839B-15 5.674B-15 8.345B-15 V2L1 2.503E-14 3.8398-14 5.674B-14 8.3453-14 1.168R-13 V2LI 1.836B-13 2.3373-13 3.338Z-13 4.6733-13 6.342B-13 V2L1 DCF for monoenerg. ground-surface source I(Oy/s)/(Bq/=2))

V2L1 1.493B-16 9.8353-17 8.181Z-17 9.7673-17 1.4361-16 V2L1 4.7851-16 7.3183-16 1.0503-15 1.4573-15 1.9101-15 V2L1 2.710B-15 3.2433-15 4.1941-15 5.3863-15 6.759B-15 V2L1 n DCF for semi-infinite monoener. cloud arc j(Sv/s)/(BE/q0)3 V2L1 7.690Z-16 1.467Z-15 2.717R-15 4.416B-15 6.737B-15 V2L1 2.0732-14 3.193R-14 4.7543-14 7.1081-14 1.012z-13 V2L1 1.6241-13 2.0893-13 3.030Z-13 4.305B-13 5.922E-13 V2L1 SZ V2L1 1.471E+01 2.186E+01 1.7443+01 2.5361+01 V2L1 decay constants and branching fractions V2LI V2L1

.00000+00

.000Z100

.0003+00

.OO0+.00 V2L1

-group phot/dis, and ICRP-38 betas (MeV/din)

V2L1

.0001.00

.OOOE+00

.0001+00

.0003+00

.000+.00 V2L1

.000E+00

.oooe+00

.0001+00

.OOOE+00

.0001+00 V2L1

.000+00

.ooo0+00

.0003+00

.OOO300

.0001.00 V2Ll V2L1 em DCrc - Air 1-r, Grnd shine, Inbal/Clasa V V2L1

.OOOR+00 2.7503-18

.0008+00

.OOOE300

.000!+00 V2L1 3.3103-19

.0001+00

.000Z+00 V2L1

.000+00

.0001+00

.0003+00

.OOOE+00

.000r.*00 V2L1

.000+00

.oooe000

.0003+00

.000+00 V2L1 1.730Z-11 1.7303-11 1.730R-11 1.730Z-11 1.730R-11 V2L1 1.73O0-11

.0001+00

.0003o+00 V2L1 3.125E-06 4.723R-06 3.772Z-06 5.4673-06 V2L1 decay constants and branching fractions V2L1 V2L1

.000003+00

.000003E00

.0001+00

.0003+00 V2L1

-group phot/dis, and ICRP-38 betas (MeV/dil)

V2L1

.000X+00

.0003+00

.0003.00

.0001+00

.0003+00 V2L1

.0001+00

.OOO+00

.0001+00

.0003+00 V2L1

.0oooe00

.000N+00

.OOO+00

.000oe00

.0001+00 V2L1 46 47

8 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 72 ICRP-38 Orgi 73

.0003+00 74

.000X+00 75

.000H+00 76

.000+00 77 1.730B-11 78 1.730R-11 79 2

C 14 (Src Ci) 80 Decay chain, 81 C 14 82 1.380161-08 83 ORIOEr-2 18-84

.000E.00 8S

.0OOO+00 86

.0003+00

A PNPS-Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 Page 84 87 88 89 90 91 92 4.*9403-02 ICRP-38 Organ 2.590Z-19 1.540B-19 2.220Z-20 1.030Z-20 DCra - Air i=mer, arnd shine, IXnal/Class c 3.520R-19 l.530E-19 1.210Z-19 7.060Z-19 2.240B-19

.000Z+00

.OOOE+00 2.430E-16 2.520B-20 8.650E-21 7.250E-21 4.630Z-20 1.610B-20

.0001+00

.0OOE+00 7.460Z-20 V2L1 V2L1 2.1908-19 V2L1 V2L1 1.2503-20 V2L1 V2L1 84 85 86 87 88 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 LISTING Or INPUT DATA PATHWAY OPTION u

3 (COMP.

A --> SITE)

COMPARTMENT A:

Refueling Level TOTAL FREE AIR VOLUME (ci ft)

FILTERED RECIRCULATION RATE (cfm)

LMAM RATE TO ATMOSPHERE (frae/day)

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.

(INSTANTANEOUS RELEASE FROM SOURCE) 7.0001+05

.000.+00 9.6008+01 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 AREVA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-505258901 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 85 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 2

.0000 3

.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 2

BR r

3 zZ

1. OOOE00 2.850E-03

.OOOR+00

.0001+00 2.150Z-03

.0001+00

.000B+00

.000x+00

.0001+00 ELEMENT ZZ* STANDS FOR THE RBMAINrNG DATA-LIBRARY ELXMZNTS/NUCLXDES NOT LISTED ABOVE, IF ANY.

A ARE VA PNPS-Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by, John N. Hamawi Page 86 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 (bourn)

.0000E+00 5.0000E-01 5.0000e 1.0000E+00 1.0000e+00 -

2.0000E+00 CONCEN"R.

X/Q (sec/m3) 7.4793-04 7.479X-04 7.4793-04 GAMMA

%/Q (se /w=3) 3.1993-04 3.199Z-04 3.199E-04 DEPOSITION D/Q (1/m2)

.0003+00

.000e+00

.000e+00 BREATHING RATE

(.3/sec) 3.500R-04

3. 500Z-04 3.500Z-04 EXR.FILT.

BYPASS FRACTION

.000R+00

.000E+00

.0003+00 COMPART. C rNT.FILTER BYPASS FR.

.0003+00

.000Z+00

.OOO+.00 COMPART. C OCCUPANCY FACTOR 1.oooe+00 1.000E+00

1. 000E+00 TIME INTERVAL (hours)

.0000E+00 - 5.0000E-01 5.0000Z 1.0000X+00 1.0000R+00 -

2.00003+00 COMPART A

MULTIPLIERS (IF APPLICABLE)

LEM RATE REC.YILTER 1.000Z+00 1.000B+00 1.0003+00 1.000+00 1.000+00 1.000+00 COMPART B

MULTIPLIERS (IF APPLICABLE)

LEAK RATE REC.FILTER 1.000Z+00 1.000Z+00 1.0003Z00 1.0003+00 1.0003E00 1.0003+00 COMPART C MULTIPLIERS (IF APPLICABLE)

INTAKE/EXE REC.FILTXR 1.0003+00 1.0003+00 1.0003+00 1.000+00 1.0003+00 1.0003E00 FLOW KULT.

SPRAYBD ARBA TO UNSPRAYED

1. 0003+00

1. 0003+00 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)

NUCLIDE BR 82K BR 82 BR 83 BR 84m BR 84 BR 85 BR 86 BR 87 BR 88 KR 83M KR 85K KR 85 GROUP 2

2 2

1 1

1 (c

7.89203+01 2.0420E+02 2.5670z+03 1.3290s+02 4.73303+03 5 *81503+03 4.3560R+03 9.92103+03 1.13003+04 2.5670E+03 5.8900oo03

8. 5510z+02 USER-SPECIFIED SOURCE INVENTORY NUCLIDS CROUP (CL)

KR 87 1

1.17503.04 XR 88 1

1.66203+04 RR 89 1

2.0960Z+04 FR 90 1

2.08103+04 1128 2

5.7020r+02 1129 2

1.79303-03 1130M 2

5.40203+02 1130 2

1.38303+03 1131 2

2.71703+04 1132 2

2.4110E+04 1133 2

3.41703.04 X134M 2

4.07403+03 NUCLIDE 1134 r135 1136K 1136 X3131-K X3133M X3133 X31353 X3135 X3137 X3138 X1139 GROUP 2

2 2

2 1

1 1

1 (CI)

3. 8150+04 3.18203+04 9.44603+03 1.54403+04 1.90503+02 1.05203+03 3.41703+04 6.82503+03 1.7440E+04 3.0070B+04 3.03703+04 2.44703+04

A AR 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 ID 32-5052589-01 Page 87 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 BR 83 2

2.4352r+00 BR 84 2

1.10578-10 BR 83M 1

9.44453+00 KR 85M 1

1.45053.02 KR 85 1

8.5501Z+02 KR 87 1

2.47293-02 KR 88 1

4.7443U+01 8R 89 1128 1129 1130M 1130 X131 X132 1133 X134 X135 X3131M 3

9.0150Z-01 2

2.54193-15 2

1.7930B-03 2

3.69633-46 2

3.61473+02 2

2.49263+04 2

1.74193+01 2

1.53579+04 2

2.18963-04 2

2.5697E.03 1

1.96063+02 XE133M' X8133 X1l35M X1135 SZ138 csl3S C8137 C5138 C8139 B137M B1139 1

9.46699+02 1

3.28693+04 1

4.1160E+02 1

9.60503+03 1

7.77763-27 3

6.60143-06 3

7.29873-03 3

8.23373-10 3

1.41353-43 3

6.9045B-03 3

1.27008-03 RE 87 RB 88 RB 89 3

3.6297E-ll 3

5.29253.01 3

1.6731E-25

-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 ID 32-5052589-01 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 NUCLIDE COMPARTS.

A (Ci/m3)

BR 82 3.219B-05 BR 83 6.143B-07 BR 84 2.789Z-17 KR 83W 4.765B-04 RR 85M 7.318B-03 XR 85 4.314Z-02 XR 87 1.248B-06 XR 88 2.3943-03 DISTRIBUTION OF RADIOACTIVITY X128 X129 1130M 1130 1131 1132 1133 1134 1135 XR131H X2133M XR133 XE135 XE138 6.412B-22

.5238-10 9.324B-53 9.118Z-05 6.288Z-03 4.394E-06 3.8741-03 5.523Z-11 6.4821-04 9.8911-03 4.776E-02 1.6581.00 2.077E-02 4.846Z-01 3.9241-31 CHEM-SPRAY IN COMP.

A (CO)

.000Z+00

. 000Z+00

.OOOZ1400

.000B+00

. 0001+00

.000o+00

.0001.00

. 0001+00

.0001+00

.0001.00

.000X+00

.000H+00

.000Z+00

.0001+00

.000+E00

.OOO+00

.0001E00

.O00E+00

.000Z+00

.0001+00

. 000+00 RZC.FILTSR IN COMP. A (CI)

.0001+00

.000E+00

.OOO+00

.000Z+00

.000z+00

.0001+00

.OOO+00

.0001+00

.0003+00

.OOO+00

.OOOZ+00

.0001+00

.0001.00

.000R+00 COMPARTS.

B (Ci/=3)

.0001+00

.000Z+00

.0001+00

.OOO+00

.0001+00

.000H+00

.0001+00

.000Z+00

.0001+00

.OOO+00

. 000+00

.0001+00

.0001+00 RZC.FXLTIR IN COMP.

D (Ci)

.0001+00

.0001+00'

.0001+00

.000B+00

.0001+00

.000oo00

.ooo0+00

.0001+00

.000K+00 EMR.FILTER TO ATMOSP.

(CI)

.0001+00

.000X+00

.0003+00

.0001.00

.0001+00

.000+00

.0001.00

.000Z+00

.OOO+00

.000Z+00

.000E+00

.0001+00

.OOO+00

.000Z+00

.0001+00

.0001+00 OFFSITE GROUND DZP (Ci/m2)

.OOO+00

.0001+00

.000X+00

.0001+00

.OOO+00

.0001+00

.000B+00

.OOO+00

.000Z+00

.0005+00

.0001+00

.0005+00

.OOO+00

.000E+00

.0001+00

.000R+00

.OOO+00

.0001.00 TOTALS GROUP GROUP GROUP 1

2 3

2.275E+00 1.094Z-02

.0001+00

.0001.00

.0001+00

.000X+00

.OOO+00

.000Z+00

.0001+00

.000X+00

.0001+00

.- 000+C0

.0001+00

.OOO+00

.0001+00 GRND.TOT 2.2851+00

.0001+00

.OOO+00

.0001+00

.000Z+00 THE COMPARTMENT VOLUMES (A AND B)

IN THIS TABLE ARE1 1.982Z+04

.000B+00 (Mfi3 I

A PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWI)

A R E VA Prepared by: John N. Hamawi Document ID 32-505258901 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 NUCLIDE BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 KR 87 KR 88 1128 1129 1130K 1130 1131 1132 1133 1134 1135 XE131M

XB133M XZ133 XZ135M XZ135 XS138 TOTALS GROUP I

GROUP 2

GROUP 3

GRND.TOT WITHOUT DECAY IN TRANSIT REL.

RATE INTRV REL CUML. REL CLOUD CONC (CL/hr)

(C1)

(CIM (CI/m3) 2.S52E+00

.0001.00

.000.+00 5.302Z-07 4.870B-02

.000+00

.000+00 1.012b-08 2.211Z-12

.0002+00

.OOOZ+OO 4.594E-19 3.778E+01

.OOO+00

.000+00 7.848Z-06 5.8021+02

.00Z+00

.0001+00 1.2051-04 3.420E+03

.0001.00

.000Z+00 7.105E-04 9.892E-02

.0001+00

.0001+00 2.0551-08 1.898E+02

.OOO+00

.0001+00 3.943e-05 5.084Z-17

.000+.00

.000100 1.056E-23 3.586E-05

.OOO+00

.OOO+00 7.450B-12 7.393Z-48

.OOO+00

.0001+00 1.5361-54 7.229z+00

.OOO00

.0001+00 1.502B-06 4.9852+02

.0001+00

.000Z+00 1.036E-04 3.4842-01

.000Z+00

.0001.00 7.2381-08 3.0711+02

.000+00

.000+00 6.381Z-05 4.379Z-06

.OOO+00

.0001+00 9.098Z-13 5.139E+01

.OOO+00

.000Z+00 1.0681-05 7.843E+02

.OOO1+00

.0001+00 1.6291-04 3.7871+03

.OOO+00

.0001o00 7.8671-04 1.3151+05

.000Z+00

.0001+00 2.731Z-02 1.646E+03

.0001+00

.0001+00 3.420Z-04 3.8421+04

.0001+00

.0001+00 7.9828-03 3.111Z-26

.000+00

.0003+00 6.463Z-33 REL.

RATE (Cl/br) 2.552z+00 4.870E-02 2.211Z-12 3.7781+01 5.8023+02 3.4201+03 9.892B-02 1.898Z+02 5.0841-17 3.5861-05 7.3932-48 7.2291+00 4.985E+02 3.4841-01 3.071Z+02 4.379Z-06 5.1391+01 7.843E+02 3.7871+03 1.3151+05 1.646Z+03 3.842E+04 3.111Z-26 1.8031+05 8.6721+02

.000+00 1.812Z+05 INTRV REL (CL)

.0001+00

.000x+00

.0001.00

.000X+00

.0001+00

. OOO+00

.0001+00

.OOO+00

.0001+00

.0002.00

.0001+00

. 000x+00

.0002+00

.OOO+00

.0001+00

.0003+00

.OOO+00

.OOO.00

.0001+00

.0001+00 WITH

.0001+00 bra IN-TRANSIT CUML. REL (Cl)

.0001+00

.0002+00

.0002.00

.OOO+00

.0001.00

.0002.00

.0001.00

.0001+00

.OOOZ+00

.OOO+00

.000o+00

.0001+00

.0003+00

.0001+00

.0001.00

.0001+00

.0003.00

.0001.00

.0001+00

.0002+00 DECAY CLOUD CONC (Ci/-3) 5.302Z-07 1.012Z-08 4.5941-19 7.848E-06 1.2051-04 7.1053-04 2.055Z-08 3.9438-05 1.056Z-23 7.450e-12 1.5361-54 1.502e-06 1.036e-04 7.2381-08 6.381Z-05 9.098Z-13 1.068Z-05 1.6293-04 7.8671-04 2.731Z-02 3.420Z-04 7.982Z-03 6.463E-33 3.747B-02 1.802Z-04

.OOO+00 3.765Z-02 1.803E+05

8. 6721+02

.0001+00 1.812Z+05

.OOOZ+00

.000+00

.OOOE+00

.OOOZ+00

.OOOE+00

.000E+00

.000+00 3.7471-02 1.8021-04

.0001+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

Ii A

A AR E VA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 90 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 OUTDOOR RECEPTOR zXTzRNAL RADIATION RxPOSURE DUE TO AIRBORNE RADIOACTIVITY (INTERVAL DOSZ8 ARE FROM

.0000E+00 TO

.0000E+00 br.)

(CoNTINUOUS OCCUPANCY)

Beta Air DOSE RATE NUCLIDE (rad/hr)

BR 82 BR 83 BR 84 KR 83M XR 85M XR 85 KR 87 KR 88 R3 87 RB 88 1128 1129 1130M 1130 1131 1132 1133 1134 1135 X1131M XZ133M XZ133 X3135S XR135 XE138 C8135 CS138 1.311Z-04 5.782Z-06 1.004E-15 5.402E-04 S.473R-02 3.165R-01 4.8391-05 2.554-02

.000z+00

.0001+00 1.4053-20 8.453Z-10

.0003.00 7.938z-04 3.531R-02 6.375B-OS 4.659e-02 1.007Z-09 6.969B-03 4.167E-02 2.690B-01 6.5921+00 5.931B-02 4.503E.00 7.731Z-30

.000oz00

. 00o0100 Beta Air INMW DOS (rad)

.000X+00

.0001+00

.OOO+00

.0oooe00

. oooe+00

.000oo00

.0ooo+00

.000oo00

. 000+00

.0001.00

.000oo00

.OOO100

.OOOR+00

.000E+00

.000Z.00

. 000+00

.0003+00

. OOO+00

.0001+00

.OOO100

.OOO+00

.OOO00

.0001+00

.000+.00

.0001+00 Gamna Air DOSE RATE (rad/hr) 5.325-04 2.878z-08 3.123Z-16 7.691B-06 7.2491-03 5.968Z-04 6.196Z-06 2.931Z-02

.0001.00

.0001+00 3.423R-22 6.9911-11 6.937B-53

1. 223Z-03 1.5021-02 6.2821-05 1.473R-02 9.089Z-10 6.397B-03 1.2451-03 1.2451-02 4.7223-01 5.620B-02 7.5271-01 2.766Z-30

.0001.00

.0001.00 Gamat Air INTVL DOS (rad)

.000OZ00

.000+.00

.0001+00

.0001.00

.000+.00

.0001+00

.0003+00

.0001+00

.OOO+00

.0001+00

.0001.00

.OOO+00

.000E+00

.0001z+O

.000+.00

.0001.00

.0003+00

.OOOR+OO

.0001+00

.OOO+00

.0003+00

.0001.00

.0003+00 Tot. Skin DOSE RATE (rew/hr) 4.887z-04 2.4611-06 7.877Z-16

1. 941-06 2.7991-02 1.2431-01 3.035-OS 3.6821-02

.0003.00

.0001+00

7. 1921-21 6.292Z-11 5.6321-53 1.355-03 2.4491-02 8.188Z-05 3.3113-02 1.2421-09 8.4721-03 9.568B-03 9.765Z-02 1.3584+00 7.303Z-02 2.4871+00 6.0271-30

.0001+00

.000o+00 Tot. Skin INTVL DOS (rea)

.OOO+00

.0003400

.000E+00

.000E.00

.0001.00

.0003.00

.0003+00

.000H400

.0001+00

.0001.00

.0001+00

.0001.00

.0001+00

.0001.00

.0003+00

.0003.00

.0001+00

.0003+00

.0001+00

. OOOS+OO

.000.+00

.0001.00

.000E+00 Thyroid DOWS RITE (rem/br) 3.927Z-04 2.191Z-08 2.487E-16 2.875Z-08 5.034Z-03 4.777Z-04 4.8351-06 2.314B-02

.0003.00

.000X+00 2.4851-22 1 638Z-1

.000.+00 8.8993-04

1. 0683-02

4. 6181-05

1. 065Z-02 6.738Z-10

4. 873Z-03

3. 6301-04

6. 096B-03 2.350Z-01 3.9753-02 5.366Z-01 2.1253-30

.0003.00

.000.00 Thyroid IITVL DOS (rem)

.000.+00

.0001.00

.0001+00

.OOO+00

.0001+00

.000+00

.0001+00

. 000Z+00

.000E+00

.0001+00

.000Z+00

.0001+00

. 000X+00

.00O1+00

.OOO+00

.0003+00

.0003Z00

.OOO+00

.0001+00

.000H+00

.0003+00

.0003.00

.0001+00

.0001+00 Bff D.E.

DOSE RATE (r/b/hr) 3.9271-04 2.202Z-08 2.463B-16 6.707B-08

5. 137B-03 4.8173-04

4. 824-06

2. 291Z-02

.000E+00

.0001+00 2.5033-22

1. 613Z-11

.0003+00

8. 899Z-04 1.074E-02 4.6183-05

1. 0693-02

6. 7383-10 4.8541-03

3. 6111-04

6. 1403-03

2. 4283-01 3.975Z-02 5.4123-01 2.125Z-30

.000R.00

.0003+00 1ff D.E.

INTVL, DoS (re=)

.0001+00

.0001.00

.000X+00

.OOO+00

.0001+00

.0003+00

.OOO00

.0003+00

.0001+00

.000H+00

.0001+00

.0003+00

.000+00

.0001.00

.0001+00

.000O+00

.000.+00

.0001+00

.OOO+00

.0001+00

.0001.00 JI

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 ID 32.5052589-01 Page 91 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 OUTDOOR RECEPTOR Beta Air DOSE RATE (rad/hr)

EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (INTERVAL DOSES ARE YROM

.0000E+00 TO

.OOOO00 hre)

(CONTINUOUS OCCUPANCY)

Beta Air INTVL DOS (red)

.0003+00

. 0001+00

.000.+00 aOc-n Air DOSE RATE (rad/hr) 1.3323+00 3.797B-02

.0003.00 GOain Air INTVL DOS (rad)

.0003+00

. 0003+00

.000R+00 Tot. Skin DOSE RATE (rem/hr) 4.2155+00 6.799Z-02

.000.+00 Tot. Skin INTVL DOS (rem)

.000z+00

.0001+00

.0003.00 Gonads DOSE RATE (rem/br) 8.S613-01 2.6963-02

.0003+00 Gonads INTVL DOS (rem)

.0003+00

.0003+00 Breast DOSE RATE (rem/hr) 9.939R-01 3.0793-02

.0003+00 Breast INTVL DOS (ren)

.0003+00

.0001+00

.OOO+500 GROUP 1

GROUP 2

GROUP 3

1.1863+01 8.9873-02

.000oe00 GRND.TOT 1.195E+01 CUM. TOTAL FROM TnO Lungs DOSE RATE (rem/hr)

GROUP 1 7.9141-01 GROUP 2 2.6841-02 GROUP 3

.0001.00

. 000M+00

.OOO+00 Lung.

INTVL DOS (rem)

.0003+00

.0001.00

.000z+00 1.3705+00

.0003+00

.0003+00 R.Narrow DOSS RATE (ren/hr) 7.228B-01 2.596B-02

.0001+00 R.Marrow.

INVVL DOS (rem)

.0003+00

.000.E00

.0001+00 4.2835+00 Done Sur DOSE RATE (rem/hr) 2.0965+00 4.705E-02

.0001+00

.0003+00 Bone Sur INTVL DOS (rem)

.0003.00

.0003+00 8.83 1-01 Thyroid DOSE RATZ (rem/hr) 8.4653-01 2.7533-02

.0001+00

.0003+00

.0003+00 Thyroid INMVL DOS (rem)

.000Z+00

.OOO.00

.0003+00 1.0253+00 Remaindr DOSE RATS (rem/br) 7.5333-01 2.562E-02

.0005+00

.0001+00

.0003+00 Remaindr INTVL DOS (rem)

.000+00

.0003+00

.0005+00 GRND.TOT 8.1833-01 CUM. TOTAL YROM TnO Eff D.E.

DOSE RATE (rem/hr)

GROUP 1

8.5873-01 GROUP 2

2.7613-02 GROUP 3

.0003+00

.ooo0+00 Zff D.E.

INTVL DOS (rem)

.0003+00

.oooe+00

.0003.00 7.487x-01 TID Thy DOSS RATE (rem/hr)

.0005+00

.0003+00

.000Z+00

.0003+00

.0003o00 TID? Thy INTVL DOS (rem)

.OOO3+00

.000x+00

.0003+00 2.143s0oo RG1109WB DOE RATE (rem/br) 1.2233+00 3.567Z-02

.OOOs+00

.000+.00

.0003+00 8.7403-01

.OOO+00

.000.+00 7.789s-01

.000E+00

.000o+00 R1O109WB INTVL DOS (rem)

. 0003+00

.0003+00

.0003+00 GRND.TOT 9.863R-01 CUM.

TOTAL MROM T-0

.0003+00

.000N+00

.000+00

.0003+00

.0003+00 1.2583+00

.000o00

.0003+00 I

A AR EVA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-50525894t Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by John N. Harnawi Page 92 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 OUTDOOR RECEPTOR NUCLIDI BR 82 BR 83 BR 84 KR 83M KR 85H KR 85 KR 87 XR 88 RADIATION EXPOSURE DUE TO INHALATION (INTERVAL DOSES ARE ?ROM

.00001+00 To

.00001+00 hrs).

Thyroid DOSZ RATE (rem/hr) 5.092E-04

5. 377E-08 6.6821-18

.0001+00

.odoz+OO

.000E+00

.0008+00 0001+,00 (CONTINUOUS OCCUPANCY)

PR 87 RD 88 X128 X129

.OOO+00

.000Z+00 2.629E-21 S.41*E-os Tbyroid INTVL DOS (rem)

.000z+OO

.0001+00

.000Z+00

.0001.00

.0003+00

. 000+00

.000+00

.0o0o0oo

.0001+00

.000z+00

. 0001+00

.0001+00

.OOO+00

.000oo00

. 0003+00

.0001+00

.OOO+OO

.000+00

.0001+00

.000Z+00

.00oz+00

.000z.00

.000+00

.OOOE+00 zff D.E.

DOSE RATE (reu/hr) 1.0211-03 1.1371-06 S.5S901-17

.0001+00

.OOO+00

.0001+00

.OOO+00

.0001+00

.OOOE+00 6.303E-22 1.6291-06

.000E+00 4.999E-03 4.2921+00 3.4751-05 4.700B-01

1. *506-10 1.653B-02

.0001+00

.00011+00

.000E+00

.0001+00

.000H+00

.0001+00

. 000o+00 Eff D.E.

INTVL DOS (rem)

.0001+00

.OOOB+00

.OOO+00

.0001+00

.000oo00

.0001+00

.000Z+00 OOOE+00

.000+00

.OOOZ+00

.0003+00

.0001o+00

.000+00

.00000oo

.000o+00

.0001o+00

.0001+00

.000+00

.000e+00

.OOOE+00

.000+00

.0001+00

.000X+00

.OOOB+OO 1130M 1130 1131 1132 I133 1134 1135 XB13 m

. OOO+.00 1.393E-01

1. 4101+02 5.871l-04 XZ133M X1133 xz135M XE135 X1139 C513S C8138

1. 4461+01 1.2228-09 4.211R-01

.000o+00

.000+00

.OCOE+00

.000oz00

.OOO0+00

.000Z+00

.0003+00

.0001+00

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Altemalive Source Term Methodology (2038 MWt)

A R EVA Prepared by: John N. Hamawi Document ID 32-5052589-01 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 OUTDOOR RECEPTOR RADIATION EXPOSURE DUE TO INHALATION (INTERVAL DOSES ARE FROM

.00003+00 TO OOOOE+00 hrD)

Gonad.

DOSE RATE (rem/hr)

. 0003+00 1.9483-02

.0003+00 (CONTINUOUS OCCUPANCY)

Gonads INTVL DOS (rem)

.0003+00

.0003400 GROUP 1

GROUP 2

GROUP 3

GRND.TOT CUM. TOTAL FROM T-0 Lunge DOSE RATE (rem/hr) 1.9483-02

.0003+00

.000E+00 Breast DOSE RATE (rem/hr)

.0003+00 4.882Z-02

.0003+00 4*.882-02 Remsindr DOSE RATE (rem/hr)

.OOO+00 5.738B-02

.0003+00 5.738B-02 Breast 1NTVL DOS (rem)

.0003+00

.0003+00 Remaindr NTvL DOS (rem)

.OOO+00

.0003+00

.000B+00

.0003+00 GROUP 1

GROUP 2

GROUP 3

.000Z00 5.916B-01

.000+00 GRND.TOT 5.9168-01 CUM.

TOTAL FROM T=0 Bff D.E.

DOSE RATE (rem/hr)

Lungs INTVL DOS (rem)

.0003+00

.0001+00

.OOO00

.000.+00

.0003+00 3ff D.E.

INTVL DOS (rem)

.0003+00

.000E+00

.0003+00 R.Marrow DOSE RATE (rem/hr)

.0003+00

4. 029o-02

.000+00 4.029B-02 TID Thy DOSE RATE (rez/hr)

.000R+00 2.2703+02

.000B+00 R.Marrow INTVL DOS (ram)

.0003+00

.000E+00

.0003+00 Bone Bur DOSE RATE (rem/hr)

.000Z+00 3.6923-02

.000s+00 3.692B-02 Bone Bur INTVL DOS (rem)

.0003+00

.0003+00 Thyroid DOSE RATE (rem/hr)

.000Q+00 1.560E+02

.0003+00 1.560B+02 Thyroid INrVL DOS (rem)

.0003o00

.0003+00

.0OOO+00

.000E+00 TID Thy SNTVL DOS (rem)

.00o0+00

.0003+00

.0ooo+00 GROUP 1

GROUP 2

GROUP 3

.000E+00 4.785e+00

.000e+00 GRND.TOT 4.785E+00 C8M. TOTAL FROM TuO

.0003+00

.0003+00 2.270B+02

.0003+00

A AREVA PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 94 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

OUDOOR RECEPTOR TOTAL RADIATION EXPOSURES (AIR IMNBRSION PLUS INRALATION)

(CONTINUOUS OCCUPANCY) eota Air DOSE RATE T (hours)

(rad/br)

.00003+00 5.0000E-01 1.0000E+00 2.0000E+00 1.19E501 1.640E+00 2.568E-01 4.394Z-02 Beta Air INTVL DOS (red)

.0003+00 2.5893+00 3.655Z-01 9.395E-02 Gonads INTVL DOS (rem)

Beta Air Cox. DOSE (rad)

.0003.00 2.5893400 2.954Z+00 3.048E+00 Conado CUM.

DOSE (rem)

Ga=& Air DOSE RATE (rad/hr) 1.3703+00 1.9943-01 4.6333-02 2.1463-02 Breast DOSE RATE (rem/hr)

GaCa Air INTVL DOS (rad)

.*000.E00 2.988E-01 4.938B-02 2.776Z-02 Breast 1NTVY DOS (rem)

Geiina Air CUM.

DoSE (rad)

.0003+00 2.9883-01 3.4823-01 3.7593-01 Breast CUM. DOSE (rem)

Tat. skin DOSE RATE (rvn/hr) 4.2833400

'6.023B-01 1.117B-01 3.491E-02 Lungs DOSE RATE (rem/hr)

Tot. Skin INTVL DOS (rem)

.000.R00 9.315B-01 1.3993-01 5.346E-02 Lungs INTVL DOS (rem)

Tot. Skin CUM. DOSE (rem)

.000+00 9.315-01 1.071E+00

1. 125+00 Lungs CII.

DOSE (rem)

Gonads DOSE RATE T (hours)

(rem/br)

.0000R+00 5.0000Z-01 1.00003+00 2.00003+00

- 9.0253-01 2.3183-01 3.124E-02 1.4853-02

..00O+00 1.9708-01 3.285B-02 1.9023-02

.000B100 1.9703-01 2.2983-01 2.4883-01

.. 1.073B+00 1.564E-01 3.650Z-02 1.701E-02

.0003+00 2.3423-01 3.8783-02 2.196X-02

.0003+00 2.3423-01 2.7303-01 2.9493-01 1.4103+00 2.0203-01 4.050B-02 1.480-02

.0003+00 3.0793-01 4.794Z-02 2.1118-02

.0003+00 3.0793-01 3.558Z-01 3.769E-01 R.Marro.

DOSE RATE T (hours)

(rem/br)

.00003+00 5.0000Z-01 1.00003+00 2.00003+00 7.890E-01 1.1618-01 2.840E-02 1.404Z-02 R.Marrow INT DOS (rem)

.0003+00 1.724E-01 2.9213-02 1.772E-02 Remaindr INTV, DOS (rem)

.0003+00 1.8278-01 3.058Z-02 1.784Z-02 R.Marrow CUM.

DOSE (rem)

.0003+00 1.7243-ol 2.0163-01 2.193B-01 RE indr CUM.

DOSE (rem)

.0003+00 1.827Z-01 2.1333-01 2.3113-01 Bone Sur DOSE RATE (rem/hr) 2.180E+00 3.116E-01 6.650S-02 2.7293-02 Eff D.E.

DOSE RATE (rem/hr) 5.671E+00 7.756B-01 1.183B-01 1.671E-02 Bone Sur INTVL DOS (rem)

.0003.00 4.7403-01 7.5228-02 3.704E-02 Zff D.E.

INTVL DOS (rem)

.000+00 1.2273+00 1.719B-01 4.0583-02 Bone Sur CUM.

DOSE (rem)

.000E+00 4.7403-01 5.492E-01 5.862B-01 Zff D.E.

CUM. DOSE (rem)

.0003+00 1.227Z+00 1.3993+00 1.4393+00 Thyroid DOWE RATE (rem/br) 1.5693+02 2.1173+01 2.8693+00 C6.675Z-02

TID Thy DOSE RATE (rem/hr)

.2.2703+02

3.059Z+01 44.122B+00

,7.487B-02 Thyroid INTVL DOS (re=)

.OOO+00 3.388Z+01 4.5763+00 7.147E-01 TID Thy INTVL DOS (rem)

.000B+00 4.8993+01

6. 602S+00

1. 0103+00 Thyroid CUM.

DOSE (rem)

.000+00 3.3883.01 3.845R+01 3.917Z+01 TID Thy CUM.

DOSE (rem)

.0003+00 4.899Z+01 5.559Z+01 5.660Z+01 Remaindr DOSE RATE T (hours)

(rem/br)

.0000E+00

5. 0000Z-01 1.0000Z+00 2.00003+00 8.363Z-01 1.2253-01 2.9193-02 1.396E-02

/

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Temm Methodology (2038 MWt)

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)

.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 Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

A R EVA Prepared by: John N. Hamawi Page 96 ELISA-2 (LICENSING s

SZVERZ 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)

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 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

.001 1

.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 mm END Or ANALYSIS

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 ID 32.5052589-01 Page 97 ELISA-2 Run Case #C - Main Output File

A ARE VA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

Prepared by: John N. Hamawi Page 98 6

6

666###6*

6 1

8 66668 6

6 68668 6

68666 6666666 6

6 86868 8

6 8688668 6

6 6

66866 8

i 0§#

8 66668 8 6##I#

0 6#

8668##

- 1. 1. 1. 44 8

6 8

8 8#

6666 666 6

6 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....-----..

DATA LIBRARY FILE.....

t OUTPUT FILE...........

s PROTON SPECTRA FILE 81 s PHOTON SPECTRA FILM 62:

elina2 -FEA-LPZ.e11

/SCL/eliua2-2. 2/e1isa2-2.1b elisa2-FHA-LPZ.o12 e1iza2-FHA-LPZ.e13 ellia2-FHA-LPZ.e14

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 ID 32-5052589-01 Page 99 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 Seq.

1 2

3 A

S 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 1

2 3

4 5

6 7

8 9

10 11 12 1234567890123456789012345678901234567890123456789012345678901234567890123456789012345678901234567890123&5678901234567890 PNPS AST -

FRA -

BOUNDING SRC -

24 RR DECAY -

RD VENT RELEASES -

LPZ wIazma X/Q 10002 3

6 8

1 0

NNYNNN N

NNN YYYYYY 10003 0

1.0 24.0 0.0 0.0 10004 3

0 0

1 1.0001+00

.OOO+00.000Z+00 KR XE 2

2.8508-03 2.1508-03

.000+.00 BR 1

3 0.000.+00

.0001.00

.0001+00 ZZ 10006

-1.0001+00

.0001+00 BR82 2.042E+02 BR82M 7.892Z+01 BR83 2.567R+03 BR84 4.7331+03 BR84M 1.328Z+02 BR85 5.815E+03 8R86 4.3561+03 BR87 9.921E+03 BR88 1.1301+04 1128 5.7021.02 1129 1.793E-03 1130 1.383E+03 1130M 5.4021+02 T131 2.7171+04 1132 2.411E+04 1133 3.417E.04 1134 3.8151.04 1134M 4.0741+03 1135 3.1821.04 1136 1.5441+04 1136K 9.446R+03 HR83M 2.567E+03 KR85 0.5511+02 ZR85M 5.8801+03 HR87 1.1751.04 KMeB 1.6621+04 KR89 2.0961+04 KR90 2.0811.04 XB131M 1.9051+02 XB133 3.4171.04 X1133M 1.0521+03 X8135 1.7443+04 XE13SM 6.8251.03 XB137 3.0071.04 XB138 3.0371.04 XB139 2.4471+04 10007 2 7.01.05 96.0 0.0 0.0 0.0 0.0

'Refueling Level' 10010 4

0.0 0.5 1.0 720.0 10018 5

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 10019 5

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 10021 3

0.0 3.53-04 8.0 1.81-04 24.0 2.33-04 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 ID 32-5052589-01 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 Seq.

2 3

4 5

6 7

B 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1

2 3

4 5

6 7

8 9

10 11 12 12345678901234567090123456799012345678901234567890123456789012345678901234S6713901234567890123456789012345678901234567890 ELSSA-2 DATA LIBRARY -

BASED ON ORIGEN-2 AND FEDERAL GUIDANCE REPORTS 11 AND 12 V2LI RELEASE DATEt 6/28/2004 V2L2 REMARKS (START)

V2L1 Source inventories are in Ci for the vow r level specified for each plant.

V2L1 Decay constants are in inverse hourn.

V2LI The entry line following the decay chains includes the decay constants V2L1 for each of three nembers rparent (P),

daugher (D) and granddaughter V2LI (0)], and the branching fractions (P-D),

(D-G) and (P-G).

V2LI Air imeraion DCrs are in

(((Sr or Gy))/s)/(B/n3)1, for semi-infinite cloud V2L1 Ground-ohine DCTs are in

(((Sv or Oy))/s)/(Dq/m2)] (surface contamination).

V2L1 Inhalation DCrs are in tSv/Bq).

V2L1 The inhalation DCF'a are for the Lung Clearance Class which yields the V2Ll highest Effective Dose Equivalent (Eff D.3.)l the class in identified.

V2L1 Negative DCF entries imply 'data not available'.

V2L1 ORGAN 'TID Thy' Thyroid inhalation based on TID-14844 -

lodines only.

V2L1 ORGAN 'RGl1O9WB' Whole body gaz=& dose using the Reg. Guide 1.109 DCFa.

V2L2 Skin DCrc are included along with the organ DCrn, but skin ia not V2L1 considered as an organ.

V2L1 6/28/2004 V2L2 Added beta MeV/dis for BR85, KRB9, 3R90, RM90M, RB90, 1136, Xel37 & C3-139 V2L2 (Based on Kocher, DOE/TIC-11026, Radioactive Decay Data Tables (1981)

V2L2 2

1 3

4 5

7a 9

10 11 12 13 14 15 16 17 is 2

3 4

19 20 21 22 23 24 25 26 27 28 29 READ FORMATS FOR TUE RADIONUCLIDE DATA BASE Line I

Nuclide name and source inventories (Note:

Nuclide sequence No.

is not used)

Line 2

Reader Line 3

Decay chain (3 members)

Line A

Decay constants & branching fractions Line 5

Reader Lines 6-9 18 ORIGEN-2 photons and 1 ICRP-38 beta Line 10 Header Lines 11-16 Done conversion factors (4x,a6,10x,4e12.3)

(a80)

(9x,3(a6,6x))

(Sx,6o12.3)

(aso)

(Sx,6e12.3)

(aso)

(8x,6.12.3)

V2L1 V2L1 V2L1 V2L1 V2L1 V2LI V2L1 V2L1 V2L1 V2L1 V2L1 32 END REMARKS 33 34 35 36 37 38 39 40 41 42 43 44 45 GENERAL DATA BASE 10 (ORGAN NAMES -

READ FORMAT (11x,6(a8,4x))1 Gonads Breast Lungs R.Marr Renaindr 3ff D.E.

TID Thy RG1109 4

(Power plants and power levels (NWt)

REA PWR (33 GWD/MT 3.2S) 1.000+00 PWR (50 GWD/MT 4.2%)

1.000E+00 BWR (27.5 GWD/MT 3%)

1.0008+00 BWR (40 GWD/MT 3.4%)

1.000R+00 18

[ORIaEN-2 upper limit energy in each gamna 2.0008-02 3.000Z-02 4.500O-02 7.000Z 3.0008-01 4.50OZ-01 7.00O0-01 1.000Z 2.500Z+00 3.OOOE+00 4.0003+00 6.000B V2L1 30 V2L1 31 ow Bone Sur Thyroid V2L1 WB (Skin)

V2L1 S FORMAT (llx,a20,1xe12.3) V2L1 V2L1 V2LI V2L1 V2L1 group (MeV) (8x,6e12.3)1 V2L1

-02 1.000Z-01 1.500R-01 V2LI

+00 1.5003+00 2.000R+00 V2L1

+00 8.000R+00 1.100E401 V2LI 32 33 34 35 36 37 38 39 40 d1 42

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

A R E VA Prepared by: John N. Hamawi Document ID 32-5052589-01 Page 101

6

'7 a8 3

Factors to 1.0 1.0 convert data library DC?. to proper units, an shown Convert air Iersion DCF to [((SB or (y)/s)/(Bq/m3)I Convert ground shine DCY to [((8v or Oy)Iu)/(Bq/m2)J V2L1 V2L1 V2L1 43 44 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 Seq.

1 2

3 4

5 6

7 8

9 10 11 12 12345678901234567890123456799012345678901234567890123456789012345678901231567890123456789012345C789012345C789012345C7890 1.0 18 Air gama 6.6763-16 1.5023-14 1.S02Z-13 18 Air gAfa 1.8291-16 2.7603-16 2.3258-15 18 Skin ga=

1.138z-16 1.2393-14 1.317Z-13 Convert inbalation DCF to [By/Ba]

DCr for semi-infinite monoener. cloud arc j(Gy/a)/(9q/n3)j 1.6693-15 2.503E-15 3.839E-15 5.674Z-15 8.345Z-15 2.503R-14 3.839e-l4 5.674Z-14 8.3453-14 1.168Z-13 1.836B-13 2.337Z-13 3.3381-13 4.673Z-13 6.342C-13 DCF for monoenerg. ground-surface source [(Oy/s)/(Bq/m2)]

1.493B-16 9.8353-17 8.181R-17 9.7673-17 1.4368-16 4.785Z-16 7.318B-16 1.0501-13 1.457Z-15 1.910Z-15 2.7103-15 3.2431-15 4.1941-15 5.3861-15 6.759r-15 tDCr for semi-infinite monoener. cloud src t(Sv/s)/(Bq/=3)1 7.690r-16 1.4671-15 2.717R-1S 4.416R-15 6.737r-15 2.073E-14 3.1931-14 4.7543-14 7.1083-14 1.0123-13 1.624g-13 2.0893-13 3.030E-13 4.305Z-13 5.922B-13 V2L1 46 V2L1 47 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 V2L1 RADIONUCLIDE DATA BASZ 1

it 3 (Sre C1) 1.4712+01 2.186E+01 1.7441+01 2.536Z+01 Decay chain, decay constants and branching fractions n

3 6.40320Z-06

.000001+00

.OOOOOE+00

.0001+00

.0001+00 ORIGEN-2 18-group phot/dLi, and ICRP-38 betas (MeV/dis)

.0001+00

. 000+00

.000Z00

.000Z+00

.0001+00

.0001.00

.0001+00

.0001.00

.000+00

.0001+00

.OOO+00

.0001+00 5.600Z-03 ICRP-38 Organ

.0001+00

.0003+00 1.730E-11 1.7301R-11 2

C 14 (Sre C1)

DCxs -

Air

.0001+00 3.310Z-19

.000z+00

.0001+00 1.730E-11 1.730E-11 3.125Z-06 iner, arnd 2.7501-18

.0001+00

.000X+00 1.7301-11

.000E+00 4.723Z-06 shine, Inhal/Class V

.0001+00

.0003.00

.0001Z00

.0001+00

.00oz+00

.0003+00

.0008+00

.0003Z00 1.730Z-11 1.730Z-11

.OOOE+00 3.772E-06 5.4673-06 V2L1 V2L1 V2L1 V2L1

.OOO+.00 V2L1 V2L1

.0001.00 V2L1

.0002300 V2L1

.0001+00 V2L1 V2L1 V2L1

.0003+00 V2L1 V2L1

.0003.00 V2L1 V2LW 1.730E-11 V2LI V2L1 V2L1 V2L1 V2LI

.OOOZ+00 V2L1 V2L1

.000OO00 V2L1

.OOO+00 V2L1

.OOO100 V2L1 V2L1 48 49 50 51 52 53 54 55 56 57 58 59 60 61, 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 Decay chain, decay constants and branching fractions C 14 1.38016Z-08

.00000R+00

.000001400

.0001400

.0001+00 ORSGZN-2 18-group phot/dis, and ICRP-38 betas (MeV/dis)

.000E+00

.0001.00

.0003+00

.000+00

.000E+00

.OOO00

.000E+00

.0001+00

.000E+00

.0001+00

.00OZ+00

.0001E00 4.940Z-02

A AR EVA 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 ID 32-5052589-01 Page 102 88 89 90 91 92 ICRP-38 Organ DCTs - Air 4 r,

ornd shine, Inhal/Cltas c 2.590Z-19 3.520Z-19 1.530B-19 1.210Z-19 7.060Z-19 1.5408-19 2.2408-19

.OOO+00

.000E+00 2.4308-16 2.220E-20 2.5208-20 8.6508-21 7.250Z-21 4.630B-20 1.0308-20 1.6108-20

.0001.00

.000R+00 7.460Z-20 V2Ll 2.190Z-19 V2L1 V2LI 1.250E-20 V2L1 V2L1 85 96 87 88 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)

FILTERED RECIRCULATION RATE (cfa) a LEA RATE TO ATMOSPHERE (frac/day)

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.

7.000E+05

.OOO+00 9.6008+01 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 PNPS - Radiological Consequences of a Design-Basis Fuel Handling Accident A

Based on the Alternative Source Term Methodology (2038 MWt)

A R E VA Prepared by, John N. Hamawi Document ID 32*5052589-01 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.

NUCL.

GROUP FORM 1.

FORM 2 FORM 3 COMPARTMENT B RECIRC.

FORM_____O______FORM__

YoRH I YORH 2 FORM 3 COMPARTMENT C RECIRC.

EXHAUST TO ATMOSPHERE INTAKE TO COMPART.

C FORM I FORK 2 FORM 3 FORM I FORM 2 FORM 3 FORM I FORM 2 FORM 3 I------

I

.0000

.0000 2

.0000

.0000 3

.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 1

KR XE 2

BR S

3 zz 1.000z+00 I

2.850B-03

.0001+00

.0001+00 2.150Z-03

.0003+00 FORM 3

.000Z00

.000E+00

.0001+00 ELEMENT ZZ' STANDS FOR THE REMAINING DATA-LIBRARY ELMENTS/NUCLIDES NOT LISTED ABOVE, IF ANY.

A ARE VA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32.5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 104 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 (hourn)

CONCZNTR.

X/Q (sc/am3) 3.692Z-05 3.692Z-OS 3.692Z-05 1.915Z-05 GQAMA X/Q (nec/m3) 3.551Z-05 3.551Z-05 3.551Z-05 1.782Z-05 DEPOSITION D/Q (1/m2)

.000E+00

. 0005+00

.OOOE+00

,0005+00 BREATHING RATS (W3/s8e) 3.5005-04 3.500X-04 3.5005-04 3.500B-04

zx5.HIL.r.

BYPASS

FRACTION

0005.00

.000Z+00

.000Z+00

.0005+00 COMPART. C INT.PILTER BYPASS YR.

.0008+00

.0005+00

.0008+00

. 000Z+00 COMPART.

C OCCUPANCY FACTOR 1.000Z+00

1. 0005+00 1.000Z00 1.0008+00

.OOOOZ+OO 5.0000o-01 1.00005+00 2.0000+00 5.0000B-01 1.0000X+00 2.00008+00 8.00008+00 8.0000z+00

2. 4000x+01 9.6000z+01 2.4000E+01 9.60005+01 7.2000E+02 1.0668-05 4.3395-06 1.1945-06 9.627B-06 3.7455-06 9.6568-07

.0005+00

.000+00 1.8005-04 2.3005-04 2.300E-04

.0005+00

..0005+00

.0008+00

.0005+00

.0008+00 1.0005+00 1.0005+00 1.0005+00 TIME INTERVAL (hours)

COMPART A

MULTIPLISRS (IF APPLICABLZ)

LEAK RAES REC.FILTZR COMPART. B MUtTIPLIBR8 (IF APPLICABLE)

LEAK RATS REC.ILTER COMPART C

MULTIPLIERS (Ir APPLICABLE)

INTAKE/23M PEC.FILTER FLOW MULT.

SPRAYED AREA TO UNSPRAYED

.0000+00 5.0000Z-01 1.0000E+00 2.00008+00 8.0000E+00 2.4000Z+01 9.6000Z+01 5.0000Z-01 1.00008+00 2.00003+00 8.0000Z+00 2.40005+01 9.60008+01 7.2000E502

1. 000Z+00 1.000S+00 1.000R+00 1.0005+00 1.000R+00

1. 0005+00

1. 000+00

1. 0005+00 1.0005+00 1.OOOS+00

1. 0005+00

1. 000.+00

1. 0005+00 1.0005+00 1.0005+00

1. 0005+00 1.0005+00 1.0005+00 1.0003+00

1. *000+00 1.0005+00

1. OOO+00 1.0005+00

1. 000Z+00

1. 000S+00

1. 000+00 1.0005+00 1.0005+00 1.0005+00 1.0005+00 1.0008+00

1. 000+00 1.0005+00 1.0001+00

1. 000Z+00 1.0008+00

1. OOOZ+00 1.0005+00

1. 0005+00

1. 000+00 1.000+00 1.o000+00 1.0008+00

1. OOOH+00 1.OOO+.00 1.0005+00 1.0005+00 1.0005+00

A AR EVA PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWQ Prepared by: John N. Hamawi Page 105 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)

NUCLIDX BR 82M BR 82 BR 83 BR 84H BR 84 BR 85 BR 86 BR 87 BR 88 KR 83M KR 85M XR 85 GROUP 2

2 2

1 2.

2.

MCiU 7.8920R+01 2.04203+02 2.5670Z+03 1.32803+02 4.7330E+03 5.8150E+03 4.35608+03 9.9210E+03 1.13006+04 2.5670Z+03 5.88003+03 8.5510E402 USER-SPECIFI8D SOURCE INVENTORY NUCLIDE GROUP (cL)

KR 87 1

1.1750E404 KR 88 1

1.6620R+04 XR 89 1

2.0960R.04 XR 90 1

2.0810Z+04 1128 2

5.7020R+02 1129 2

1.7930Z-03 1130M 2

5.40203+02 1130 2

1.38308+03 1131 2

2.71703+04 1132 2

2.41103+04 X133 2

3.4170E+04 1134M 2

4.07403+03 NUCLIDE 1134 1135 113614 1136 X313114 X313314 13133 X313514 X3135 X1137 13138 XZ139 GROUP 2

2 2

2 1

1 1

1.

(CL) 3.8150E+04 3.18201+04 9.44601+03 1.54401+04 1.905014+02 1.05208+03 3.41701+04 6.82503+03 1.7440Z.04 3.0070Z+04 3.03701+04 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 NUCLrDx BR 82 BR 83 BR 84 XR 83H KR 851 KR 85 KR 87 KR 8B RD 87 RB 88 R1B 89 INVENTORY FOLLOWING 2.4003+01 HOURS GROUP (Ci)

NUCLIDE 2

1.2761Z+02 BR 89 2

2.43523+00 1128 2

1.10573-10 1129 1

9.44453+00 11301 1

1.45053.02 1130 1

8.55013+02 1131 1

2.4729E-02 X132 1

4.74433+01 1133 3

3.62973-11 1134 3

5.29251+01 1135 3

1.67311-25 XE131M OF RADIOACTIVE GROWTH AND DECAY PRIOR TO RELEASE GROUP (CL)

NUCLIDE GROUP (CL) 3 9.0150Z-0i X813314 1

9.4669Y.+02 2

2.5419E-15 X1133 1

3.28699+04 2

1.79303-03 X3135M 1

4.11603+02 2

3.69633-46 XB135 1

9.60503+03 2

3.61473+02 X1338 1

7.7776Z-27 2

2.4926E+04 C8135 3

6.60143-06 2

1.7419E+01 CS137 3

7.29873-03 2

1.5357E+04 CSi38 3

9.23373-10 2

2.18963-04 C8139 3

1.41353-43 2

2.56973+03 BA137M 3

6.90453-03 1

1.96063+02 BA139 3

1.2700Z-03

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 ID 32-5052589l01 Page 106 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.

A (Ci/m3)

BR 82 3.219Z-0S 9R 83 6.143Z-07 BR 84 2.789Z-17 KR 83M 4.7653-04 KR 85M 7.318Z-03 KR 85 4.3143-02 KR 87 1.248Z-06 KR 89 2.394Z-03 X128 X129 1130M 1130 1131 1232 1133 1134 1135 XZ131M XB133M X3133 X31351 XZ135 XE138 6.4123-22 4.523B-10 9.324R-53 9.118B-05 6.288Z-03 4.394E-06 3.874Z-03 5.523E-11 6.4823-04 9.891Z-03 4.7763-02 1.658E+00 2.077Z-02 4.8463-01 3.924Z-31 CH=M-SPRAY IN COMP.

A (Ci)

.000+00

.0003+00

.000+00

.0003+00

.000+00

.0008+00

.0003+00

.000+00

.0003+00

.0003B00

. OOO+00

.0003+00

.000Z00

.OOO+00

. 000Z+00

. OOO0+00

.0ooo+00

.OOO00

.000o+00

.0ooo+00 REC.FILTER IN COMP. A (Ci)

.000Z+00

.000B+00

.0003+00

.00OZ+00

.0003+00

.000.+00

.0008+00

.0003+00

.000E+00

.000B+00

.0003+00

.000E+00

.0003+00

.OOO+00

.0003+00

.OOO+00 COMPARTN.

B (CL/m3)

.0003+00

.000R+00

.0003+00

.000B+00

.0008+00

.OOO+00

.0008+00

.OOO+00

.000E+00

.0003+00

.000+00

.OOO+00

.0003+00

.000+00

.0003+00

.000R+00

.OOO+00

.0003+00

.OOO+00

.000+00

.OOO+00 REC. FILTER iN COMP. B (Ci)

.0003+00

. 000Z+00

.0003+00

.0003.00

.0003+00

.0003.00

.0003+00

.OOOZ+00

.0003.00

.0003+00

.0003400

.0003+00

.000Z+00

.0002+00

.0003+00

.000B+00 ZXR.FILTBR TO ATMOSP.

(Ci)

.0003+00

.0003.00

.0003+00

.OOOR00

.0003+00

.000+00

.0003+00

.0003.00

.000+00

.000B+00

.0003+00

.000+.00

.0003+00

.000B+00

.0003+00 OFFSITE GROUND DEP (Ci/fti2)

.000+00

.0003+00

.0003+OO

.0003.00

.00O0+00

.0003+00

.0008+00

.000+00

.0003+00

.000o+00

.000B+00

.0003+00

.000B+00

.000+o0O

.000R+00

.0003+00

.000B+00

.000E+00

.0003+00

.OOO3.00

.000B+00 TOTALS GROUP GROUP GROUP 1

2 3

2.2753+00 1.0943-02

.0003+00

.000R+00

.000+00

.OOO.00

.0003+00

.OOO+00

.00OZ+00

.0003+00

.000R+00

. 000X+00

.0008+00'

.000+00

.OOO+00

.0003+00

.OOO+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.

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

A R EVA Prepared by: John N. Hamawi Document ID 32.5052589-01 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 NUCLIDE BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 KR 87 KR 88

-1128 1129 1130M 1130 1131 1132 X133 1134 1135 XZ13 iN XE133M Xg133 XB135M XB135 X 138 TOTALS GROUP 1

GROUP 2 GROUP 3

aRND.TOT WITHOUT DECAY IN TRANSIT WITH REL. RATE INTRV REL CUML. REL CLOUD CONC REL. RATE (Cl/hr)

(CL)

(Ci)

(Cim3)

(Cl/hr) 2.552E+00

.oooe000

.000+00 2.617E-08 2.552Z+00 4.870Z-02

.000+00

.oooe+00 4.9953-10 4.870B-02 2.2113-12

.0003.00

.0003+00 2.268B-20 2.21tZ-12 3.778E+01

.OOO00

.000.+00 3.8743-07 3.7783+01 5.802E+02

.OOOE+00

.OOO300 5.9503-06 5.8023+02 3.4203+03

.0003.00

.0003.00 3.5073-05 3.4203+03 9.8923-02

.0003.00

.0003+00 1.0243-09 9.8923-02 1.898.+02

.0003.00

.OOOZ+00 1.9463-06 1.898+.02 5.0843-17

.0003+00

.OOO300 5.2143-25 5.0843-17 3.5863-OS

.0003+00

.0003+00 3.6783-13 3.5863-OS 7.3933-48

.0003+00

.0003.00 7.5823-56 7.3933-48 7.229+00

.OOO3+00

.0003+00 7.414E-08 7.2293+00 4.9853+02

.OOO+00

.0003Z00 5.1133-06 4.9853+02 3.4843-01

.0003.00

.000X+00 3.5733-09 3.4843-01 3.0713+02

.0003+00

.0003+00 3.150E-06 3.0713+02 4.3793-06

.000+00

.0003+00 4.4913-14 4.379E-06 5.1393+01

.000oo00

.0003.00 5.2713-07 5.139E301 7.843.+02

.0003+00

.000+00 8.0433-06 7.843E+02 3.787E+03

.OOO+00

.000OE00 3.8843-05 3.7873+03 1.315e+05

.0003+00

.0003.00 1.3483-03 1.3153+05 1.646E+03

.000+.00

.000+00 1.688Z-05 1.6463+03 3.8428+04

.000R.00

.OOO300 3.9403-04 3.842+.04 3.111B-26

.000+.00

.0OOO+00 3.1913-34 3.1113-26

.0003+O0 hra INTRV REL (CL)

.000K.00

.0003+00 i0003.00

.0003:.00

.0003.00

.,0003+00

.0003.00

.000X.00

.0003+00

..0003+00

.0003400

.0003+00

.0003.00

.000H+00

.0003.00

'.0003400

.0003+00

.. 0003:.00 IN-TRANSXT CUML. REL (CL)

.0003+00

.000+00

.0003+00

.00O+00

.0003+00

.0003400

.000oo00

.0003+00

.000Z+00

.000z+00

.0003+00

.OOOE+00

.0003+00

.OOO+300

.OOOE+00

.000+00

.0003+00

.000+00

.OOO+00 DECAY CLOUD CONC (Ci/n3) 2.617E-08 4.9953-10 2.268B-20 3.874E-07 S.9503-06 3.507N-05 1.014B-09 1.946R-06 5.2143-25 3.6783-13 7.5823-56 7.414E-08 5.113E-06 3.573z-09 3.150E-06 4.4913-14 5.27 1-07 8.*043-06 3.8843-05 1.3483-03 1.6883-OS 3.940B-04 3.1913-34 I

1.8033+05 8.6723+02

.oooe+00 1.812R+OS

.OOO+00

.0003+00

.000e+00

.000o+00

.0003+00

.0008+00

. OOO+00 1.849E-03

8. 8943-06

.0003+00 1.8033+05 8.6723+02

.0OOO+00 1.8123+05

. ooo0000

.0003+00

.0003400

. ooo000

.0003+00

.00oz+00

.0003+00 1.849B-03 8.8943-06

.OOO+00 1.858B-03

.0003+00 1.858E-03 NOTEs THE ATMOSPHERIC CONCENTRATION OF RADIOACTIVITY I8 BASED ON A DIspERSION FACTOR (XIQ)

OF 3.6923-05 (sec/m3)

A AR EVA PNPS-Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Altem alive Source Term Methodology (2038 MWI)

Prepared by: John N. Hamawi 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 OUTDOOR RECEPTOR EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (INTERVAL DOSES ARE FROM.00001+00 TO

.00001+00 hre)

(CONTINUOUS OCCUPANCY) 8eta Air DOSE RATE NUCLIDE (rad/hr)

BR 82 6.471Z-06 BR 83 2.854E-07 BR 84 4.9573-17 KR 83M 2.667z-05 Beta Air INTVL DOS (rad)

.0001+00

.000+00

.000x+00

. 000z+00 Ganma Air DOSE RATE (rad/hr) 5.9118-05 3.194Z-09 3.467E-17 8.537B-07 camia Air rNTVL DOS (rad)

. 0001+00

.*000+00

.0001+00

.0001+00 Tot. Skin DOSE RATE (rea/hr) 5.172B-05 1.2301-07 5.560B-17 1.779Z-07 Tot. skin INTVL DOS (rem)

.0001*00

.0001+00

.0003.00

.000Z*00 Thyroid DOSE RATE (rem/hr) 4.359Z-05 2.432B-09 2.7608-17 3.1921-09 Thyroid INTVL DOS (rein)

.000H+00

.0003+00

.0003*00 Zff D.E.

DOSE RATE (rem/hr) 4.359Z-05 2.4441-09 2.7343-17 7.445B-09 1ff D.S.

IWXVL DOS (rem)

.0001*00

.0001400

.000R*00

.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 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 RB 87

.0003.00

.0005+00

.000Z+00

.OOO+.00

.0001.00

.0001+00

.0001+00 RB 88

.0001.00

.0005.00

.00O0100

.000E+00

.0003+00

.0001+00

.00O0100 1128 6.935Z-22

.0001+00 3.799B-23

.0001+00 3.724B-22

.0001+00 2.7591-23

.0001.00 2.7798-23 1129 4.1731-11

.0001400 7.760Z-12

.0001+00 5.236B-12

.0001+00 1.819B-12

.0001+00 1.7908-12 11303 1130 1131 1132 1133 1134 1135 XZ131M XB133M XZ133 XB135X XZ135 XZ138 CS135 C8138

.0003+00 3.919Z-05 1.743E-03 3.147E-06 2.3008-03

4. 970Z-11 3.4401-04 2.057Z-03 1.328Z-02 3.2541-01 2.9288-03 2.223Z-01 3.816g-31

.000o400

.0ooo000

.0ooo0oo

.000X+00

.0001400

.o000z00

.000oo00

.000o+00

. 000z+00

.0001.00

.000Z+00

.OOO+100

. 000+00

.0001+00

.0001+00 7.700E-54 1.3579-04 1.6671-03 6.9731-06 1.635S-03 1.009Z-10 7.1003-04 1.3821-04 1.3821-03 5.2411-02 6.239B-03 8.355Z-02 3.070-31

.0001.00

.OOOE+00

.000Z+00

.0001+00

.OOO+00

.OOO+100

. 000Z00

.0001+00

.0001400

. 000Z+00

.0001+00

.0008+00

.0001.00

.000+.00

.0001+00

.0001+00 6.251Z-54 1.2981-04 1.975Z-03 7.2871-06 2.392Z-03 1.0851-10 7.552-04 5.1341-04 5.342U-03 8.778B-02 6.4741-03 1.610B-01 4.4421-31

.0008+00

.000Z+00

.0001+00

.0001Z00

.00O1400

.0001+00

.0003.00

.0001+00

.0003+00

.0005+00

.0003+00

.0001+00

.OOO+00

.000+.00

.0001+00

.0001+00 9.079Z-05 1.186B-03 5.126e-06 1.182B-03

7. 4e0-11 5.4093-04 4.029Z-05 6.7661-04 2.608Z-02 4.4131-03 5.956B-02 2.358B-31

.000+.00

.0001+00

.0003+00

.0001+00

.000+00

.0001+00

.0001.00

.0008+00

.0005+00

.000+.00

.0001+00

.000z+00

.0001+00

.OOO+OO

.0001+00 9.879Z-05 1.192Z-03 5.126B-06 1.186B-03 7.4801-11 5.389B-04 4.008B-05 6.8161-04 2.695-02 4.4131-03 6.0078-02 2.3581-31

.0001+00

.0001.00

.0001+00

.OOO+.00

.OOO+00

.OOO+100

.OOO+00

.OOO+.00

.OOO+00

.000Z+00

.0001+00

.0001400

.000Z00

.0001+00

.OOO+00

.0001+00

.0001.00

.0001+00

A AR EVA PNPS - Radiological Consequences of a Oesign-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWt)

Prepared by: John N. Hamawi Page 109 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.

OUTDOOR RECEPTOR Beta Air DOSE RATE (rad/hr)

GROUP 1 5.856Z-01 GROUP 2 4.4363-03 GROUP 3

.000Z+00 GRND.TOT 5.900Z-01 CUM.

TOTAL FROM T-0 Lungs DOSE RATE (rem/hr)

EXTERNAL RADIATION EXPOSURE DUE TO AIRBORNE RADIOACTIVITY (INTERVAL DOSES ARE FROM.OOOOE+00 To

.0000Z+00 hrn)

(CONTINUOUS OCCUPANCY)

Beta Air INTVY DOS (rad)

Gama Air DOSE RATE (rad/hr)

Camn Air INTVL DOS (rad)

Tot. Skin DOSE RATE (r

/hr)

Tot. Skin INTVL DOS (rem)

GonaOd DOSE RATE (rem/hr)

Gonads INTVL DOS (rem)

Breast DOSE RATE (rem/hr)

Breast INTVI DOS (rem)

.000,+00

.OOOZ+00

. 0001Z00

.000Z+00

.0001+00 Lungs INTVL DOS.

(rem)

.OOO+00

.OOOE+OO

.000E+00 1.4793-01 4.214E-03

000E+00 1.521E-01 R.Marrow DOGE RATE (rem/hr) 8.023B-02 2.8821-03

.000o+00

.0001+00

.oooe+00

.0oooz00 R.Marrow INTVL DOS (rem)

.000Z+00

.0001+00

.0001+00 2.724Z-01 5.3111-03

.000+00 2.7771-01 Bone our DOSE RATE (rem/hr) 2.326E-01 5.222E-03

.0001+00

. OOO+OO

.000+00

.0001+00

.0001+00 Boae Sur rmrVL DOS (rem)

.0001+00

.000Z+00

.0003+00 9.503E-02 2.992Z-03

.OOO1.00 9.802Z-02 Thyroid DOSE RATE (rem/hr) 9.3961-02 3.0S6Z-03

.0001+00

.000Z+00 Thyroid rNTVL DOS (rem)

.000R+00

.000B+00

.000+00 1.103B-01 3.4171-03

.OOO+00 1.1371-01 Remaindr DOSE RATE (rem/hr) 8.362Z-02 2.8441-03

.000+00

.000Z+00

.000+00

.000E+00

.0001+00

.0001+00 Remaindr IrTVL DOS (rem)

.000+00

.000B+00 GROUP 1

GROUP 2

GROUP 3 8.785Z-02 2.980Z-03

.0001+00 GRND.TOS 9.083Z-02 CUM. TOTAL FROM T-0 Zff D.E.

DOSE RATE (rem/hr)

.000+00

.0001+00 Rff D.E.

IVL DOS (rem)

.000o+00

.0003+00

.oooe+00 8.311Z-02 TID Thy DOSE RATE (rem/hr)

.000R+00

.0003+00

.0001+00

.000R+00

.0001+00 TID Thy ILqTVL DOS (re)

.0003+00

.000B+00

.000+00 2.379E-01 RO1109WB DOSE RATE (rvn/hr) 1.3571-01 3.9603-03

.OOOE+00

. 000+00

.000B+00 9.702.-02

.000B+00 8.647B-02

.000R+00

.OOOZ+00

.000+00 RG11O9WB INTVL DOS (rem)

.0008+00

.000E+00

.0OOOZ+0O GROUP 1

GROUP 2 GROUP 3 9.532E-02 3.0658-03

.000E+00 ORND.TOS 9.83ez-02 CUM.

TOTAL FROM T=O

.OOO+00

.OOOZ+00

.000o+00

.OO0+00

.000B+00 1.397E-01

.000+00

.000X+00

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 ID 32-5052589-01 Page 1 10 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 OUTDOOR RECEPTOR RADIATION EXPOSURE DUE TO INHALATION (INTERVAL DOSES ARE FROM

.0000Z+00 T0

.00003.00 (CONTINUOUS OCCUPANCY)

NUCLTDZ BR 82 BR 83 BR 84 KR 83M KR 85M KR 85 KR 87 KR 88 RB 87 RB 88 1128 x129 1130O 1130 1131 1132 1133 X134 I135 XE131M X3133M X%133 XZ135M XE135 hro)

Thyroid DOSE RATE (rem/hr) 2.514K-05 2.6553-09 3.2993-19

.0008+00

.0003+00

000R+00

.000.+00

. 0003+00

.0003.X00

.0003+00 1.2983-22 2.61SX-06

.0003+00 6.8783-03 6.9603+00 2.898K-05 7.137Z-01 6.030B-11 2.0793-02

.000.E00

.0003+00

.000300

.000Z+00

.0003+00

.0 00+00

.0003+00

.0003+00 Thyroid rNTVL DOS (rem)

.0001+00

.0003+00

.000.+00

.000z+00

.0003.00

.0003+00

.000300

.000X+00

.0003+00

.0003.00

.0003+00

. 0003+00

.000+00

.0003+00

.OOO+00

.oooe000

.0003.00

.0003+00

. 000+.00

.0003+00

.000t00

.0003+00

.000Z00 Bff D.E.

DOSE RATE (rem/hr) 5.0403-05 5.612B-08 2.760Z-18

.0003+00

.0003.00

.0003S+00

.0003+00 3.1113-23 8.0413-08

.0003+00 2.4688-04

2.

193-01 1.7163-06 2.3203-02 7.4333-12 8.1583-04

.0003+00

.0OOO+00

.0003+00

.0003.00

.0003+00

.0003z00 8ff D.E.

INTVL DOS (rem)

.0003+00

.000H+00

.OOOE+00

.00013.00

.0003+00

.0003.00

.0003+00

.0003+.00

.0003+00

.0OOOE00

.000z+00

.0003.00

.0003+00

.0003.00

.000.E00

.0003+00

.0003+00 XB138 C9135 C8138

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 ID 32-5052589-01 Page 111 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 OUTDOOR RECEPTOR RADIATION EXPOSURE DUE TO INHALATION (IN=ERVAL DOsZs ARE FROM

.00001+00 TO

.00001+00 hra)

Gonad.

DOSB RATE (rem/hr)

(CONTINUOUS OCCUPANCY)

Gonads INTVL DOS (rem)

.0003+00

. 0003+00

. 000+00 Breast DOSE RATE (rem/br)

.000H+00 2.4101-03

.0001+00 Breast INTVL DOS (rem)

.0001+00

.0003+OO

. 0003+00 GROUP 1

GROUP 2

GROUP 3

. 00014.00 9.6163-04

.0001+00 ORND.TOT CUM.

TOTAL FROM T-0 9.6161-04

.0003+00

.000E100 Lungs DOSE RATE (rem/hr)

GROUP 1

GROUP 2

GROUP 3

.000E+00 2.920Z-02

.0001+00 GRND.TOT 2.920Z-02 CVM. TOTAL FROM TaO Xff D.E.

DOSE RATE (rem/hr)

Lungs INTVL DOS (rem)

.0001+00

. OOON+OO

.OOON+OO

.0001+00

.0003+OO

.0001+00 Xff D.E.

INMVI DOS (rem)

.0001+00

.0003+00

.0001+00 R.Marrow DOSE RATE (rem/br)

.0001S+00 1.9891-03

.0001+00 R.Marrow INTVL DOg (rem)

.0003+00

.0001+00

.000E+00 Done Sur

.DOSZ..RATE (rem/hr)

.0003.00 1.823E-03

.000z+O0 1.8233-03 Bone Sur INTVL DOS (rem)

.0003+00

.0001+00

.000O+00

.0001+00

.000Z+00 Thyroid DOSE RATE (rem/br)

.0001+00 7.7011+00

.0001+00 7.701E+00 Thyroid rNTVL DOS (rem)

.0001.00

.0001+00

.0001+00 2.4101-03 Remaindr DOSE RATE (rem/hr)

.0003+00 2.832Z-03

.0003:+00 2.8321-03

.000o+oo

.000oo00 Remaindr IZTVL DOS (rem)

.000Z+00

.0001+00

.000E+00

.OOO+00

.OO0+0O 1.989Z-03

.0001+00

.000+00 TID Thy DOSE RATE (rem/hr)

.000E+00 1.120E+01

.000E+00 TID Thy INSTV DOS (rem)

.000+00

.0008+00

.000E+00 GROUP 1

GROUP 2

GROUP 3

.000+OO 2.3628-01

.OOO+00 GRND.TOT 2.362Z-01 CUM. TOTAL FROM TO0

. OO0O+OO

.000R+00 1.1201+01

.0001+00

. OOOO+00

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

A R EVA Prepared by: John N. Hamawi Document ID 32-5052589-01 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

SUMMARY

OUTDOOR RECEPTOR BOUNDING SRC -

24 HR DECAY -

RD VENT RELEASES -

LPZ W/Gaema X/Q TOTAL RADIATION EXPOSURES (AIR IMMERSION PLUS IMNALATION)

(INSTANTANEOUS RELEASE FROM SOURCE)

(CONTINUOUS OCCUPANCY)

T (hours)

.OOOO300

5. 00003-01 1.0000.E00 2.0000Z+00 8.0000E+00 2.40003+01 9.6000R+01 7.20003+02 S (hours)

.000000Z+

5.0000Z-01 1.00003+00 2.00003+00 8.00003+00 2.4000E+01 9.60003+01 7.20002.02 T (hours)

.00003400 5.0000Z-01

1. 00003.00 2.00003+00 8.00003+00 2.40003401 9.60003+01 7.2000Z+02 Beta Air Beta Air DOSE RATE INTVL DOS (rad/hr)

(rad) 5.900R-01

.0003+00 8.097Z-02 1.2783-01 1.267Z-02 1.8043-02 2.1693-03 4.638E-03 5.7983-04 4.713Z-03 8.0493-05 2.737Z-03 1.2323-06 5.3273-04 4.270B-09 1.8903-05 Gonads DOSE RATE (rem/hr) 9.898E-02 1.447E-02 3.4463-03 1.6483-03 4.358E-04 4.5533-05 9.1443-08 8.219R-11 R.Marrow DO8B RATE (rem/hr) 8.510Z-02 1.255B-02 3.1083-03 1.557Z-03 4.1183-04 4.2603-05 6.331Z-08 4.0892-11 Gonads INTVL DOS (rem)

.0003+00 2.1603-02 3.6113-03 2.1063-03 3.632E-03 1.8443-03 1.8463-04 8.299Z-07 R.MarrOw INrV8. DOS (rem)

.0003+00 1.8603-02 3.170B-03 1.9563-03 3.4353-03 1.737Z-03 1.6853-04 S.2943-07 Beta Air CUM.

DOSE (rad)

.000Z+00 1.2783-01 1.458Z-01 1.505Z-01 1.552Z-01 1.579Z-01 1.5858-01 1.585R-01 Gonads CUM.

DOSE

.OOOZ300 2.160R-02 2.5223-02 2.732Z-02 3.0953-02 3.2803-02 3.2988-02 3.2983-02 R.Karrow CUM.

DOSE (rem)

.000E+00 1.8603-02 2.177Z-02 2.3738-02 2.7163-02 2.8903-02 2.907Z-02 2.907Z-02 GCama Air DOSE RATE (rad/hr) 1.521-01 2.2138-02 5.1433-03 2.3823-03 6.300E-04 6.6523-05 1.7193-07 2.412E-10 Breast DOSE RATE (rem/hr) 1.1623-01 1.6953-02 3.997Z-03 1.9888-03

4. 9903-04 5.225E-05 1.1093-07 1.0838-10 Bone Sur DOSE RATE (rem/hr) 2.397B-01 3.428B-02 7.3413-03 3.0293-03 7.9913-04 8.549E-05 2.723B-07 1.9063-10 Gemma Air INTVL DOS (rad)

.0003+00 3.317Z-02 5.4813-03 3.0813-03 5.2463-03 2.6743-03 2.7673-04 1.7593-06 Breast

.ISrVL DOS (rem)

.0003+00 2.5353-02 4.2173-03 2.424E-03 4* 158Z-03 2.1138-03 2.1303-04 1.0273-06 Bone Sur INTVL DoS (rem)

.0003+00 5.2123-02 8.2843-03 4.1013-03 6.646E-03 3.4042-03 3.6633-04 2.4153-06 Goms Air Tot. Skin CUM.

DOSE DOSE RATE (red)

(rem/hr)

.0003+00 2.777E-01 3.3173-02 3.9423-02 3.8653-02 7.809E-03 4.1733-02 2.8153-03 4.6973-02 7.4663-04 4.9653-02 8.160Z-05 4.993Z-02 3.4193-07 4.9933-02 1.041Z-09 Breast Lungs CUM.

DOSE DOSE RATE (ren)

(rem/hr)

.000E+00 1.200E-01 2.535E-02 1.739Z-02 2.9568-02 3.8173-03 3.199E-02 1.631Z-03 3.6143-02 4.289z-04 3.826Z-02 4.4553-05 3.8473-02 7.583E-08 3.8473-02 4.8023-ll Bone Sur Thyroid CUM. DOSE DOSE RATE (rem)

(rem/hr)

.000Z+00 7.798Z+00 5.2123-02 1.0533+00 6.0403-02 1.436E-01 6.4513-02 4.226Z-03 7.1153-02 4.4333-04 7.456Z-02.

4.619Z-05 7.492B-02 8.632E-08 7.493Z-02 7.032B-11 Tot. Skin INTVL DOS (rem)

.0003+00 6.0453-02 9.3193-03 4.0373-03 6.205E-03 3.2223-03 3.666B-04 4.820B-06 Lungs INTVL DOS (rem)

.0003+00 2.6222-02 4.2343-03 2.1783-03 3.577Z-03 1.811Z-03 1.7813-04 6.394R-07 Thyroid IMVL DOS (rem)

.OOO+00 1.6843+00 2.2793-01 3.6463-02 4.0253-03 1.8743-03 1.8613-04 7.6503-07 Tot. Skin CUM.

DOSE (rem)

.0003+00 6.0458-02 6.9773-02 7.381Z-02 8.002E-02 8.3243-02 8.360B-02 8.361E-02 Lungs CUM.

DOSE (rem)

.0003+00 2.622Z-02 3.0453-02 3.2633-02 3.621B-02 3.802Z-02 3.8203-02 3.820Z-02 Thyroid CUM.

DOSE (rem)

.OOO+00 1.6843+00 1.9123+00 1.948Z+00 1.9523.00

1. 9543+00 1.954R+00 1.9543+00

A AR EVA 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 ID 32-5052589-01 Page 113 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

OUTDOOR RECEPTOR TOTAL RADIATION EXPOSURBS (AIR I2mZRSI0N PLUS INHALATION)

(CONTINUOUS OCCUPANCY)

T (hours)

. OOOOZl00 5 00001-01 1.0000R+00 2.00001+00 Remindr DOSE RATE (rem/hr) 8.9301-02 1.311B-02 3.174E-03 1.3483-03 Rmindr INTVL DOS (rem)

.0001.00

1. 9511-02 3.2891-03 1.964E-03 Reoaindr CUM. DO8S (rem)

.0001.00

1. 9511-02 2.280B-02 2.476E-02 1ff D.e.

DOSE RATE (rem/hr) 3.346E-01 4.629Z-02 7 767E-03 1.757Z-03 Zff D.E.

INTVL DOS (rem) 0001+00 7.2493-02 1.0491-02 3.1898-03 Zff D.E.

CUM. DOSE (rem)

.0001400 7.2493-02 8.298Z-02

8. 6171-02 TID Thy DOSE RATE (rem/hr) 1.1201+01 1.5108+00 2 0351-01 3 696B-03 TID Thy INTVL DOS (rem)

.0001+00 2.4181.00

3. 259-01 4.9843-02 TID Thy CUM. DOSE (rem)

.000+.00 2 4183+00 2.7441+00 2.7941.00 8.00001400 2.4000z+01.

9.60001+01 7.20003.02 4.0931-04 4.2501-05 7.1611-08 4*874E-11 Rfl0O9Wn DOSE RATE T (hours)

(rem/hr) 3.413R-03 1.7293-03 1.6981-04

6. 103e-07 RO1109ND 2NTVL DOS (rem)

.0001+00 3.0401-02

5. 025Z-03 2.8563-03 4.8813-03 2.4851-03 2.5443-04 1.272Z-06

2. 8178-02 2.990Z-02 3.007Z-02

3. 007Z-02

4. 4403-04

4. 6311-05 8

g868-08 6.9961-11 3.7111-03

1. 8788-03 1.870Z-04 7.824Z-07 8.9881-02 6.907B-14 9.1763-02 2.8558-42 9.1951-02

.00o0400 9.1953-02 b000R+00 4.7833-04 4.9353-15 3.701Z-43

.0001+00 2.7951+00 2.795E+00 2.7951+00 2.795E+00

.0000E+00 S.0000E-01

1. 00001+00 2.0000E+00

8. 0000E+00 2.4000E+01 9.60001+01 7.20001+02

1. 397Z-01 2.0261-02 4.737Z-03 2.2163-03 5.8613-04

6. 168E-05 1.4571-07

1. 007Z-10 RO1109WB CUM. DOSE (rem)

.0003+00 3.0403-02 3.5433-02 3.8283-02

4. 3173-02 4.565Z-02 4.591B-02 4.591B-02

A PNPS -Radiological Consequences of a Design-Basis Fuel Handling Accident Document ID 32-5052589-01 Based on the Alternative Source Term Methodology (2038 MWI)

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)

Beta Air (rad)

.OOO+O0

.0001+00

.0001.00 1.585Z-01 Gaime Air (rcd)

.0001+00

.0001+00 4.993R-02 Tot. skin (rem)

.0008+00

.0001+00

.000R00 8.361g-02 (Beta Cont. (k)]

t

.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

.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 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 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. Harnawi Document ID 32-5052589-01 Page 115 RADTRAD Run Case #A - Nuclide Inventory File

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 ID 32-5052589-01 Page 116 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 none none Nuclide Co-60 7

O.OOOOE+00 O.OOOOE+OO O.OOOOE+00 002:

0.1663401096E+09 0.6000E+02 0.0 none O.OOOOE+(

none O.OOOOE+(

none O.OOOOE+t Nuclide 003:

Kr-85 1

0.3382974720E+09 0.8500E+02 8.551E+02 20 20 20 none none none Nuclide Kr-85m 1

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 004:

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

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 ID 32-5052589-01 Page 117 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+

none O.OOOOE+

none O.OOOOE+I Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 0.0 Y-9lm 0.5800E+1 Y-91 0.4200E+I none O.OOOOE+1 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 0.0 Y-92 0.1000E+t none O.OOOOE+(

none O.OOOOE+(

Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 0.0 01

-00 DO DO DO 00

)0 00 00

A AR 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 ID 32-5052589-01 Page 118 none none none 0.0000E+00 O.OOOOE+00 O.OOOOE+00 Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 0.0 none none none Nuclide Y-92 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 014:

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 none none Nuclide Zr-95 9

O.lOOOE+01 O.OOOOE+00 O.OOOOE+00 016:

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 none 0.OOOOE+00 O.OOOOE+00

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 ID 32-5052589-01 Page 119 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 none none Nuclide Ru-105 7

0.100OE+01 O.OOOOE+00 O.OOOOE+00 022:

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 none none Nuclide Rh-105 7

0.1000E+01 O.OOOOE+00 0.OOOOE+00 024:

0.1272960000E+06 0.1050E+03 0.0 none none none Nuclide O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 025:

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 ID 32-5052589-01 Page 120 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 none none Nuclide Te-127m 4

O.OOOOE+00 0.OOOOE+OO O.OOOOE+00 028:

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 none Nuclide Te-129m O.OOOOE+00 O.OOOOE+00 030:

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 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 ID 32-5052589-01 Page 121 0.1080000000E+06 0.1310E+03 0.0 Te-131 I-131 none Nuclide Te-132 4

0.2200E+00 0.7800E+00 0.OOOOE+00 032:

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

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 ID 32-5052589-01 Page 122 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 none none O.OOOOE+00 O.OOOOE+00 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 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 ID 32-5052589-01 Page 123 none O.OOO0E+00 none O.0OOOE+OO none 0.OOOOE+OO Nuclide 044:

Ba-140 6

0.11007 0.1400E 0.0 La-140 none none Nuclide La-140 9

736000E+07

+03 O.lOOOE+O1 O.OOOOE+00 O.OOOOE+00 045:

0.1449792000E+06 0.1400E+03 0.0 none O.0OOOE+1 none O.OOOOE+1 none O.OOOOE+1 Nuclide 046:

La-141 9

0.1414800000E+05 0.1410E+03 0.0 Ce-141 O.10OOE+1 none O.OOOOE+1 none O.OOOOE+1 Nuclide 047:

La-142 9

0.5550000000E+04 0.1420E+03 0.0 none O.OOOOE+1 none O.OOOOE+1 none O.OOOOE+1 Nuclide 048:

Ce-141 DO 00 00 D0 DO DO DO 20 DO 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 AR 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 ID 32*505258901 Page 124 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 none none Nuclide Nd-147 O.OOOOE+00 O.OOOOE+00

-0.0000E+0O 052:

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

0.2034i 0.23901 0.0 Pu-239 none none Nuclide Pu-238 8

0.2768f 0.23801 0.0 U-234 none none Nuclide Pu-239 8

0.75943 0.23901 0.0 U-235 none none Nuclide 720000E+06 E+03 0.1000E+01 O.OOOOE+00 O.OOOOE+00 054:

B63824E+10 E+03 0.1000E+01 O.OOOOE+00 O.OOOOE+O0 055:

336440E+12 E+03 0.1000E+01 O.OOOOE+00 O.OOOOE+00 056:

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 ID 32-5052589-01 Page 125 Pu-240 8

0.2062920312E+12 0.2400E+03 0.0 U-236 none none Nuclide Pu-241 8

0.1000E+01 0.OOOOE+00 O.OOOOE+00 057:

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 none none Nuclide Cm-242 0.1000E+01 0.OOOOE+00 O.OOOOE+00 059:

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 AR EVA 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 ID 32-5052589-01 Page 126 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 Noble Gases:

1.0000E+00 0.0000E+00 Iodine:

5.OOOE-03 0.OOOOE+00 Cesium:

0.0000E+00 O.OOOOE+00 Tellurium:

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

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

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

O.OOOOE+00 0.0000E+00 Cerium:

0.0000E+00 0.OOOOE+00 Lanthanum:

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 o.OOOOE+00 0.OOOOE+00 o.0000E+00 0.OOOOE+00 o.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Non-Radioactive Aerosols (kg):

0.OOOOE+00 0.OOOOE+00 End of Release File 0.OOOOE+00 0.OOOOE+00

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 ID 32-5052589-01 Page 127 RADTRAD Run Case #A - Main Output File

A A R 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 ID 32-5052589-01 Page 128 RADTRAD Version 3.03 (Spring 2001) run on 11/02/2004 at 15:33:14 File information Plant file Inventory file Release file Dose Conversion

= C:\\calcs\\calcs-PNPS\\AST\\AST-FHA\\PNPS-RADTRAD-FHA.psf

= c:\\calcs\\calcs-pnps\\ast\\ast-fha\\pnps-radtrad-fha.nif

= c:\\calcs\\calcs-pnps\\ast\\ast-fha\\non_loca.rft file = c:\\software\\radtrad\\defaults\\fgrll&12.inp t

1. 1. 1. 41 it it 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 AR 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 ID 32-5052589-01 Page 129 3.4280E+04 0

0 0

Pathways:

3 Pathway 1:

FHA Release 1

2 4

via RB Vent 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 Overlying Pool:

0 O.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

4.3000E-01 l.OOOOE+00

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 ID 32-5052589-01 Page 130 0

1 0

0 0

Compartment 3:

0 1

0 0

Pathways:

3 Pathway 1:'

0 0

1 2

2.4000 E+01 2.6000E+01 0

Pathway 2:

0 0

0 1

2 2.4000E+01 7.4400E+02 0

0 0

0 Pathway 3:

0 0

9.6000E+03 O.OOOOE+00 9.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

A AREVA 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 ID 32-5052589-01 Page 131 0

0 0

1 2

2.4000E+01 7.4400E+02 9.OOOOE+03 O.OOOOE+00 O.OOOOE+OO O.OOOOE+00 0.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 2.6000E+01 1

4 2.4000E+O1 3.2000E+01 4.8000E+01 7.4400E+02 0

Location 2:

LPZ 2

1 2

2.4000E+01 2.6000E+01 1

4 2.4000E+01 3.2000E+01 4.8000E+01 7.4400E+02 0

Location 3:

CR 3

0 1

2 2.4000E+01 7.4400E+02 1

4 2.4000E+01 4.8000E+01 1.2000E+02 7.4790E-04 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+O0 3.6920E-05 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 1.OOOOE+OO 6.OOOOE-O1 4.OOOOE-01

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 ID 32-5052589-01 Page 132 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

11 0

0 End of Scenario File

.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 ID 32-5052589-01 Page 133 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 Inlet Pathway Number 3: CR exhaust Exit Pathway Number 2: CR intake via RB Vent 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 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 ID 32-5052589-01 Page 134 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 NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.001000 hr 1.0000E+00 5.0000E-03 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs O.OO0OE+oo 0.0000E+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs O. OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 RELEASE MASS (gm) 2.-371E+00 1.311E-03 0.000E+00 O.OOOE+00 0.000E+00 o.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 Inventory Power =

1.

MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 I-131 1-132 I-133 I-134 1-135 Xe-133 Xe-135 Nuclide Kr-85m Kr-87 Kr-88 I-131 1-133 I-135 Xe-135 Group Specific Inventory (Ci/MWt) 1 8.551E+02 1

5.880E+03 1

1.175E+04 1

1.662E+04 2

2.717E+04 2

2.411E+04 2

3.417E+04 2

3.815E+04 2

3.182E+04 1

3.417E+04 1

1.744E+04 half life (s) 3.383E+08 1.613E+04 4.578E+03 1.022E+04 6.947E+05 8.280E+03

7. 488E+04 3.156E+03 2.380E+04 4.532E+05 3.272E+04 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1.560E-15 1.190E-14 Inhaled Thyroid (Sv/Bq)

0. OOOE+00

0. 000E+00 0.OOOE+00 0.OOOE+00 2.920E-07 1.740E-09 4.860E-08 2.880E-10 8.460E-09 0.OOOE+00 0.OOOE+00 n

Daughter none none none none none none none Inhaled Effective (Sv/Bq) 0.OOOE+00 0.OOOE+O0 0.OOOE+00 0.OOOE+00 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 0.000E+00 0.OOOE+00 Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Daughter Kr-85 Rb-87 Rb-88 Xe-131m Xe-133m Xe-135m Cs-135 Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 Daughter none none none none Xe-133 Xe-135 none Fractior 0.00 0.00 0.00 0.00 0.97 0.85 0.00 Iodine fractions Aerosol 0.0000E+00

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 ID 32-5052589-01 Page 135 Elemental Organic

=

5.7000E-01

=

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) 2.4000E+01 2.6000E+01 Flow Rate (% / day) 9.6000E+03 0.OOOOE+CO Pathway number 2: CR intake Pathway Filter: Removal Data Time (hr) 2.4000E+O1 7.4400E+02 Flow Rate (cfm) 9.OOOOE+03 0.OOOOE+00 Filte3 Aerosol o.OOOOE+00 o.OOOOE+00

Efficiencies Elemental O.OOOOE+00 0.OOOOE+00 s(%)

Organic O.OOOOE+00 0.0000E+00 Pathway number 3: CR exhaust Pathway Filter: Removal Data Time (hr) 2.4000E+01 7.4400E+02 Flow Rate (cfm) 9.OOOOE+03 O.OOOOE+00 Filter Efficiencies (%)

Aerosol Elemental Organic O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location EAB Location X/Q Data Time (hr) 2.4000E+01 2.6000E+01 is in compartment 2

X/Q (s

m'^-3) 7.4790E-04 0.OOOOE+00 Location Breathing Time (hr) 2.4000E+01 3.2000E+01 4.8000E+01 7.4400E+02 Location LPZ i.

Location X/Q Data Time (hr)

Rate Data Breathing Rate (mA3

sec^-l) 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00

. in compartment 2

X/Q (S

MA -3)

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 ID 32-5052589-01 Page 136 2.4000E+01 2.6000E+O1 Location Breathi Time (hr) 2.4000E+O1 3.2000E+01 4.8000E+01 7.4400E+02 Location CR Location X/Q Dat Time (hr) 2.4000E+O1 2.6000E+01 Location Breathi Time (hr) 2.4000E+01 7.4400E+02 Location Occupar Time (hr) 2.4000E+01 4.8000E+0l 1.2000E+02 7.4400E+02 3.6920E-05 O.OOOOE+00

.ng Rate Data Breathing Rate (m^3

secA-1) 3.5000E-04 1.80OOE-04 2.3000E-04 O.OOOOE+00 is in compartment 3

X/Q (s

mA-3) 1.7600E-03 O.OOOOE+00

.ng Rate Data Breathing Rate (mA3

secA-1) 3.5000E-04 O.OOOOE+00 icy Factor Data Occupancy Factor 1.OOOOE+00 6.OOOOE-O1 4-.0000E-01 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time O.OOOOE+OO Time step O.OOOOE+OO

A AR 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 ID 32-5052589-01 Page 137

1. T#Version303(Spring###2001ru######

on10### 2 0##a###

t1#5###314###

RADTRAD Version 3.03 (Spring 2001) run on 11/02/2004 at 15:33:14

4#4##4#44444###*44########§i§#####4###4444##4*4

1. 1. 4#44##4#44#4####

444

§#444 44444 4

4 #

4

4 #

4 44 #

44#

4 4

4

4##4#

4 44 #

4 4

4# #

§###

1. 44 444#4 4

4 4

4 4#*#4#44####4###*#b#####4##fi4#########4######4I#J44#4###*44##44##4444#

Dose Output 4AB4#44Doses:

4*####4444*4

444#4

1. 4*###

EAB Doses:

Time (h) =

24.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body 9.0948E-04 9.0948E-04 Thyroid 7.7828E-02 7.7828E-02 TEDE 3.2957E-03 3.2957E-03 LPZ Doses:

Time (h) =

24.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.4896E-05 4.4896E-05 Thyroid 3.8420E-03 3.8420E-03 TEDE 1.6269E-04 1.6269E-04 CR Doses:

Time (h) =

24.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body 3.6762E-07 3.6762E-07 Thyroid 1.0820E-03 1.0820E-03 TEDE 3.3541E-05 3.3541E-05 EAB Doses:

Time (h) =

26.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.4903E-01 4.4994E-0l Thyroid 3.8823E+01 3.8901E+01 TEDE 1.6393E+00 1.6426E+00 LPZ Doses:

Time (h) =

26.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.2166E-02 2.2211E-02 Thyroid 1.9165E+00 1.9203E+00 TEDE 8.0924E-02

8. 1087E-02 CR Doses:

Time (h) =

26.0000 Delta dose (rem)

Whole Body 2.9136E-02 Thyroid 8.6972E+0l TEDE 2.6956E+00

A AREVA 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 138 Accumulated dose (rem) 2.9137E-02 8.6974E+0l 2.6956E+00 EAB Doses:

Time (h) =

32.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+O0 4.4994E-01 Thyroid O.OOOOE+O0 3.8901E+01 TEDE O.OOOOE+00 1.6426E+00 LPZ Doses:

Time (h) =

32.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.2211E-02 Thyroid O.OOOOE+00 1.9203E+00 TEDE O.OOOOE+00 8.1087E-02 CR Doses:

Time (h) =

32.0000 Whole Body Delta dose (rem) 3.8136E-06 Accumulated dose (rem) - :2.9140E Thyroid 1.2410E-02 8:6986E+01 TEDE 3.8413E-04

.2.6960E+00 EAB Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 4.4994E-0l Thyroid O.OOOOE+00 3.8901E+01 TEDE O.OOOOE+00

1. 6426E+00 LPZ Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.2211E-02 Thyroid O.OOOOE+00 1.9203E+00 TEDE O.OOOOE+00 8.1087E-02 CR Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.5484E-47 2.9140E-02 Thyroid 1.0706E-43 8.6986E+01 TEDE 3.3026E-45 2.6960E+00 EAB Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 4.4994E-01 Thyroid O.OOOOE+00 3.8901E+01 TEDE O.OOOOE+00 1.6426E+00 LPZ Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.2211E-02 Thyroid O.OOOOE+00 1.9203E+00 TEDE 0.OOOOE+00 8.1087E-02 CR Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.0254-156 2.9140E-02 Thyroid 1.3267-152 8.6986E+01 TEDE 4.0729-154 2.6960E+00

A AR 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 ID 32-5052589-01 Page 139 EAB Doses:

Time (h) = 744.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 4.4994E-01 Thyroid 0.OOOOE+00 3.8901E+01 TEDE O.OOOOE+00 1.6426E+00 LPZ Doses:

Time (h) = 744.0000 Whole Body Delta dose {rem)

O.OOOOE+00 Accumulated dose (rem) 2.2211E-02 Thyroid O.OOOOE+00 1.9203E+00 TEDE O.OOOOE+00 8.1087E-02 CR Doses:

Time (h)

= 744.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.9140E-02 Thyroid O.OOOOE+00 8.6986E+01 TEDE O.OOOOE+00 2.6960E+00 837 I-131 Summary Time (hr) 24.000 24.001

24. 401 24.701 25.001 25.301 25.601 25.901 26.000 26.300 26.600 26.900 27.200 27.500 27.800 28.100 28.400 28.700 29.000 29.3 00 29.600 29.900 30.200 30.500 30.800 31.100 31.4 00 31.700 32.000 32.300 Refuel Floor 1-131 (Curies) 6.9161E+01 1.2438E+02 2.5076E+01 7.5445E+00 2.2699E+00 6.8295E-01 2.0548E-01 6.1822E-02 4.1592E-02 4.1547E-02 4.1503E-02 4.1458E-02 4.1413E-02 4.1369E-02 4.1324E-02 4.1280E-02 4.1235E-02 4.1191E-02 4.1146E-02 4.1102E-02 4.105SE-02 4.1013E-02 4.0969E-02 4.0925E-02 4.0881E-02 4.0837E-02 4.0793E-02 4.0749E-02 4.0705E-02 4.0661E-02 Atmosphere 1-131 (Curies) 7.6874E-02 2.4892E-01 9.9444E+01 1.1696E+02 1.2223E+02 1.2381E+02 1.2429E+02 1.2443E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 Control Room 1-131 (Curies) 5.7301E-04 1.8511E-03 6.3225E-02 1.9191E-02 5.7754E-03 1.7377E-03 5.2281E-04 1.5730E-04 1.0582E-04 9.3694E-07 8.2955E-09 7.3447E-11 6.5028E-13 5.7575E-15 5.0975E-17 4.5132E-19 3.9959E-21 3.5379E-23 3.1324E-25 2.7734E-27 2.4555E-29 2.1740E-31 1.9248E-33 1.7042E-35 1.5089E-37 1.3359E-39 1.1828E-41 1.0472E-43 9.2719E-46 8.2091E-48

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. Hamnawi Document ID 32-5052589-01 Page 140 32.600 32.900 33.200 33.500 33.800 34.100 34.400

48. 000 120. 000 744. 000 4.0618E-02 4.0574E-02 4.0530E-02 4.0487E-02 4.0443E-02 4.0399E-02 4.0356E-02 3.8432E-02 2.9673E-02 3.1542E-03 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02 1.2445E+02

1. 2445E+02 7.2682E-50 6.4351E-52 5.6975E-54 5.0445E-56 4.4662E-58 3.9543E-60 3.5011E-62 3.0019-155 O.OOOOE+00 O.OOOOE+00 Cumulative Dose Summary EAB LPZ CR Time Thyroid (hr)

(rem) 24.000 0.0000E+00 24.001 7.7828E-02 24.401 3.1093E+01 24.701 3.6563E+01 25.001 3.8207E+01 25.301 3.8701E+01 25.601 3.8850E+01 25.901 3.8894E+01 26.000 3.8901E+01 26.300 3.8901E+01 26.600 3.8901E+01 26.900 3.8901E+01 27.200 3.8901E+01 27.500 3.8901E+01 27.800 3.8901E+01 28.100 3.8901E+01 28.400 3.8901E+01 28.700 3.8901E+01 29.000 3.8901E+01 29.300 3.8901E+01 29.600 3.8901E+01 29.900 3.8901E+01 30.200 3.8901E+01 30.500 3.8901E+01 30.800 3.8901E+0l 31.100 3.8901E+01 31.400 3.8901E+01 31.700 3.8901E+01 32.000 3.8901E+01 32.300 3.8901E+01 32.600 3.8901E+01 32.900 3.8901E+01 33.200 3.8901E+01 33.500 3.8901E+01 33.800 3.8901E+01 34.100 3.8901E+01 34.400 3.8901E+01 48.000 3.8901E+01 TEDE (rem)

O.OOOOE+00 3.2957E-03 1.3148E+00 1.5448E+00 1.6137E+00 1.6343E+00 1.6405E+00 1.6423E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00

1. 6426E+00 1.6426E+00 1.6426E+00

1. 6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 1.6426E+00 Thyroid (rem)

O.00E+00 3.8420E-03 1.5349E+00 1.8049E+00 1.8861E+00 1.9105E+00 1.9178E+00 1.9200E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 1.9203E+00 TEDE Thyroid (rem)

(rem)

O.000E+00 0.0000E+00 1.6269E-04 1.0820E-03 6.4904E-02 6.2088E+01 7.6260E-02 7.9502E+01 7.9660E-02 8.4756E+01 8.0678E-02 8.6336E+01 8.0983E-02 8.6811E+01 8.1074E-02 8.6953E+01 8.1087E-02 8.6974E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 8.1087E-02 8.6986E+01 TEDE (rem)

O.OOOOE+00 3.3541E-05 1.9245E+00 2.4642E+00 2.6269E+00 2.6759E+00 2.6906E+00 2.6950E+00 2.6956E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00 2.6960E+00

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 ID 32-5052589-01 Page 141 120.000 3.8901E+01 1.6426E+00 1.9203E+00 8.1087E-02 8.6986E+O1 2.6960E+O0 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 (hr) 24.0 Whole Body (rem) 4.4994E-01 Thyroid (rem) 3.8901E+01 TEDE

(rem) 1.6426E+00

ML043650061

Text

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Dear Mr. Cacciapouti:

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