Text

Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability
	ML20217E117
Person / Time
Site:	Three Mile Island
Issue date:	03/17/1998
From:	Boughton K; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20217E040	List: E000-98-012, Forwards Rev 0 to Topical Rept TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident for Review & Approval by 980630 to Support Planned TS Change Requests Addressing TMI-1 NRC Insp Open Items; ML20217E081; ML20217E117; ML20217E166; ML20217E197;
References
	C-1101-826-E540, C-1101-826-E540-020, C-1101-826-E540-20, NUDOCS 9803300387
	Download: ML20217E117 (92)
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Calculation

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Code - Control Room Habitability Yes No f is this calculation within the OQA Plan Scope? X 0 (If Yes, a venfication is required)

Does this calculation contain assumptions / design input that requires confirmation? O X ,

(If Yes, provide EDTTS No.(s))

{

is this calculation performed as a design basis calculation? X 0 (If Yes, identify design basis parameters (section 3.3))

X/Q for yard intake concentration determination t

Reference Source Documents (Calculations, Safety Evaluatiens) (Section 4.3.1.3)

DOCUMENT NO. REV.NO.

I t

1 s l l

1 i

APPROVALS: I Originator Date

/

K.G. Boughton[f(A 6 O f.s7 78

Date Venfication Engineer / Reviewer Y \iTl~ ll]L')Gh& b '} b Section Manager / Date

\C&A40 5 . (l Y c 6 4 % i 98 U

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Ghou NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C 110182ti E540-020 0 2 of 9 7.--

Table of Contents 1.0 Purpose 3 2.0 Summary of Results 3 3.0 References 4 4.0 Assumptions 6 5.0 Design input 7 6.0 overall Approach and Methodology 10 7.0 Calculations 11 8.0 Appendices Appendix A - Partial Site Plan 12 Appendix 8 - Meteorological Data Files 14 Appendix C -Yard intake X/Q's & Cumulative Frequency Distribution 15 Appendix D - Dr. Ramsdell Correspondence 24 Appendix E - Expanded Output Files 30 Appendix F - 1996 Met Data QA 31 Appendix G - PLG Letter- MET DATA Files 34

GPU NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code- Control Room Habitability C 1101-826-E540 020 0 3 or 77

1. Purpose 1

The pnmary purpose of this calculation is to detem1ine yard X/Q 's for the yard ventilation intake location at various l time intervals. These values shall be used in the radiological dose assessment for control room habitability.

This calculation does not determine X/Q values for the control room ventilation system exhaust point which becomes an intake under certain failure condrtions within the ventilation system. Other analysis (Ref. 3.16 and 3.17) provide the determination of X/Q values at the exhaust point. Information is contained in this document for historical purposes supporting the decision not to use ARCON96 code for the exhaust point as it is not recommended by the author of the code.

This calculation shall serve as input to the dose assessment calculation.

2. Summary of Results Yard Intake X/Q 's 02 Hrs. 1.70E-04 sec /m^3 28 Hrs. 1.14E-04 sec /m^3 8 24 Hrs. 4.60E 05 sec/m^3 1-4 Day 3.65E-05 sec /m^3 4 30 Day 3.03E 05 sec/m^3

NUCLEA# -

CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Cale. No. Rev.No. Sheet No.

Code- Control Room Habitability C 1101826 E540-020 0 4 of fL

3. References 3.1 ARCON96 Software Package # 001169 IBM PCOO,

Atmospheric Relative Concentrations in Building l Wakes *, supplied from U.S. Department of Energy, Energy Science and Technology Software Center, I (NUREG/CR-6331 Rev.1). .

1 3.2 TMI meteorological data files:

l

.3.2.1 Tmimet76. arc 3.2.2 Tmimet78. arc 3.2.3 Tmimet80. arc 3.2.4 Tmimet81. arc 3.2.5 Tmimet82. arc 3.2.6 Tmimet96. arc i

3.3 GPUN Dwg.1E 120-01-001 Rev. 47, Site Plan - Units No.1 & 2,'Above Ground Facilities

j l

)

3.4 GPUN Dwg.1E 154-02-001,

General Arrangement Auxiliary Building and Air intake Tunnel

l 3.5 GPUN Dwg.1D 908-16-1000 Rev.1,

Meteorological Station Block Diagram TMl Unit # 1& #2' 3.6 Gilbert Associates Inc. Dwg. No. E 421030 Rev. 7,

Reactor Building Concrete Exterior Wall - Concrete Outline"

~

3.7 Gilbert Associates Inc. Dwg. No. E 102 041 Rev. 7, " Architectural West Elevation - North End*

3.8 Gilbert Associates Inc. Dwg. No. E 102-042 Rev.10, " West Elevation - South End' 3.9 Gilbert Associates Inc. Dwg. No. E 311843 Rev. 20, ' Building Service Ventilation, C!ontrol Building Plan at 306'-0* and 285'-0*.*

3.10 TID-24190, Meteorology and Atomic Energy 1968 David H. Slade, EditorJuly 1968 3.11 Gilbert Associates Inc. Dwg. No. E 101-111 Rev.12, " Architectural Roof Plan - Turbine. Auxiliary and Service Building

l 3.12 Gilbert Associates Inc. Dwg. No. B-311-839 Rev. IAO," Control Building Relief Air Duct Modification

j 3.13 NUREG -0800, U.S. NRC Standard Review Plan 6.4, " Control Room Habitabikty System' 1

l 3.14 K.G. Murphy and K.M. Campe,' Nuclear Power Plant Control Room Ventilation System Design for Meeting General Design Cnterion 19*,13 th AEC Air C!canina Ccnference. Aucu:t 1974 l

l

GPU NUCLEAR CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C 1101826-E540-020 0 5 of 92.

3.15 PLG Letter from Mark J. Abrams to Ken Boughton dated 2/11/98,

Subject:

PLG review of meteorological data 1976,1978,1980,1981, and 1982 for TMl-1.

3.16 GPUN Calculation C-1101 826-E540-022, " Estimate of (X/Q)u Values for TMI-1 Control Building Ventilation System Exhaust *, James Halitsky (Consultant) 3.17 GPUN Calculation C-1101826-E540-025, "X/Q @ TMl Ventilation System Exhaust" l

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NUCLEAR CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No- Sheet No.

Code - Control Room Habitability C-110t 826 E540-020 0 6 of 92, 4.0 Assumptions 4.1 X/Q values are determined for a diffuse reactor building leak in lieu of a point source. This is consistent with integrated containment leakage assumptions for MHA (maximum hypothetical accident). Ground Level releases are assumed for X/O determination consistent with the methodology referenced in SRP 6.4 (i.e. Murphy / Campe), References 3.13 and 3.14.

4.2 A containment diffuse leakage area is represented by an effective width and effedive height. The effective width, determined from the projected containment cross section, is the diameter of the containment. The effective height is determined as the one half of the containment height. This is consistent with Example 5 presentation in reference 3.1 and the guidance from Dr. Ramsdell(Ref. Appendix D). The diffuse area is used as a representation of an equivalent point source upstream of the containment and is used for determining initial diffusion coefficients (I y and I z).

4.3 Surface roughness length for use in the ARCON96 code is assumed as the default value of .1 m. This represents a land surface slightly higher than 60 cm grass and less than fully grown roots as defined in reference 3.10, p. 73. This is conservative in that the site and surrounding area can be considered as a small town with a significant number of trees which would yield a higher surface roughness fength. The impact of assuming a conservative roughness length (lower value) is slightly higher X/Q values.

4.4 Minimum wind speed is assumed at 0.5 m/s (1 mph) which is consistent with standard meteorologice!

practice for defining calms (Ref. 3.10). This is the default value used in the ARCON96 code and is used for applying low wind speed corrections for calm conditions.

4.5 A Sector averaging constant is assumed at 4 the default value in the code. This will result in averaging sectors with a width of 22.5

which is appropriate for the source receptor distance modeled at the yard intake. The ARCON96 code provides a parameter as an adjustment to the model for unstable conditions and short distances where sector average concentrations exceed centertine concentrations.

Gipu NUCLEAR CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitabthty C 1101826-E540 020 0 7 or y't 5.0 Design input 5.1 Site Geometry Source / Receptor Distance - Yard Intake = 300 Ft. (91 m) Ref. 3.3 as illustrated Appendix A.

Yard intake Height Above Grade = 12 Ft. ( 3.7 m), [Elev. 312'- 300'] Ref. 3.4 Section F F.

5.2 Meteorological Data Files The meteorological data files presented for use in this calculation represent hourly averages for wind speed.

wind direction, and stability class from the 100 Ft. (30.48 m) measurement height of raw meteorological data. Measurement heights of referenced data are indicated in reference 3.5. Wind speed has been converted from miles per hour to meters per second. Wind direction is in degrees. North at 360* and South at 180a A single measurement height is provided for the Met Data and is acceptable per the guidance in ARCON96 (Ref. 3.1). The met files have been prepared from raw data and presented in the format as desenbed in section 4.4.2 of ARCON96 (Ref. 3.15 and Appendix F ). Direction (bearing) of intake to yartt source is 050' (Ref. 3.3).

5.3 Building Area Building area as used in ARCON96 controls the distance downwind at which the wake effect will exist and have influence on contaminant dispersion. For this calculation the containment structure only will be used for this purpose. This is conservative since other adjacent structures will enhance the effect of the wake and assure greater dispersion of the contaminant. Per the ARCON96 code a characteristic length representing the distance the wake effect will be felt is determined as the square root of the building area.

Considering the cross sectional area of the containment. the yard intake location is clearly within the wake zone of the containment. The input calculation of area here is for purposes of satisfying the input requirement of the code and providing a somewhat real estimate of containment cross-sectional area. It is not a significant input for the TMl case determination of X/Q. Failure to provide a reasonable value will result in X/Q determination assuming normal dispersion without considenng the effects of building wake.

GPU MUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON95 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C Ilui-826-E540-020 0 8 or f 2, Containment Cross-sectional Area:

The containment cross sectional area is determined as the cross-sectional area of a cylinder and upper segment of a hemispherical shape. The following dimensions are taken from Reference 3.6.

Cylinder :

'& 141' - 6* --D '

f h q j Elev. 447' 9"

( y Elev. 303' Cylinder Cross section = Diameter x Height

= 141.5 x 144.75

= 20482 Ft.^2 (1903 m ^2)

Hemispherical Segment:

'& L _,

[c a a 4 Elev. 471*-4" H2

,w R

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s.y 9

Gipu -

NUCLEAR CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code- Control Room Habitability C 1101826-E540-020 0 9 or 72 a = Containment Radius = 70' 9* (21.6 m) Ref. 3.6 L = Containment Dia. = 141' 6* (43.1 m) Ref. 3.6 Hi= 23.6 Ft. (7.2 m), [Elev. 471'-4* - Elev. 447' 9'] Ref. 3.6 R = 113 Ft. (34.4 m) Ref. 3.6 2

H2= (R _ ,2)os = 88.1 Ft. (26.9 m) sin (a/2) = a/R

=.6261 a/2 = Sin (.6261)

= 38.8

a = 77.6 *

= 1.354 radians Arc Length c = R a

= 153 Ft. (46.6 m)

Area Full Segment (defined by a, c & R):

Ars = .5 Rc

= 8644.5 Ft. ^2 ( 803.1 m^2)

Triangular Area of Segment (defined by a, Diameter (2a), and R):

Ar = .5 L H2

= 6233 Ft. ^2 (579 m ^2)

Area Hemisphere Segment:

Ass = Ass , Ar

= 2411.5 Ft. ^2 (224 m ^2)

Total Building Cross-sectional Area As = Cylinder Cross section + Hemisphere Segment

= 22893.5 Ft. ^2 ( 2127 m ^2)

I GPU NUCLEAR CALCULATION SHEET l

i

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C i101826-E540-020 0 10 of /7. - .

I 5.4 initial Diffusion Coeffidents Initial diffusion coeffidents are determined because this analysis assumes a diffuse leak. The diffuse leak can be represented by a virtual point source with diffusion coeffidents determined at the containment structure. Perthe guidance in ARCON96 and that provided by Dr. Ramsdell(Appendix D) the fo!!owing defines the initial diffusion coeffidents used in this model:

I, Determination:

I, = Effective Width / 4.3 Ref. 3.1

= 43.1/4.3 Effective Width = Containment Dia. (43.1 m)

= 10 m L Determination:

L = Containment Height / 2 Ref. 3.1

= 51.3 / 2 Containment Height = 51.3 m

= 25.65 m [Elev. 471'-4* - Elev. 303']

Ref. 3.7 & 3.8 6.0 hethodology This analysis uses the ARCON96 computer code (Ref. 3.1) for determining X/Q values. This is an approved NRC code and has not been modified for this application. The input to this code consists of site meteorological data and assumptions as defined in this calculation. Dr. Ramsdell, the author of this code has been consulted for guidance on its use. See attached Appendix D correspondence.

9 Gau NUCLEAR CALCULATION SHEET

Subject:

Aunospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C-I101-826-E540-020 0 1I of 92.

7.0 Calculation Yard X/Q's input File -TMlYARD.RSF Output File - TMlYARD. LOG l

4

f Gau NUCLEAR CALCULATION 5HEET

Subject:

Atmosphenc Transport X/Q *s Using ARCON96 Cale. No. Rev.No. Sheet No.

Code-Control Room Habitability C-1101826-E540-020 0 12 of f 2 l

APPENDlX A PARTIAL SITE PLAN 5

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(c>u MUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q *s Using ARCON96 Calc. No. Rev No Sheet No.

Code - Control Room Habitability C 1101-826 E540-020 0 14 of 9 7.--

APPENDlX B METEOROLOGICAL DATA FILES 9

9

(apu NUCLEA# CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q s Using ARCON96 Calc. No. Rev.No. , Sheet No.

Code - Control Room Habitability C-1101-826-E540420 0 15 of 97 APPENDlX C YARD INTAKE X/Q'S CUMULATNE FREQUENCY DISTRIBUTIONS

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(c>u NUCLEA R CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev No. Sheet No.

. Code - Control Room Habitability C 1101826-E540-020 0 16 of 9 2. ,

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i N o . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . .

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I C 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 T -

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s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _

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Q

/ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

X ty 1 3 9 4 0 3 0 4 1 5 4 8 9 4 1 6 9 1 5 2 8 8 8 8 8 8 8 8 8 8 8 1 2 9 15 9 4 6 6 7 8 8 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9

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i 9 2 6 8 9 1 8 8 nd os 9 5 6 0 2 4 4 7 0 1 1

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A c im 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E hre oo . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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C - - - - - - - - - - - - - - - - - - - - - - - - - - i -

b'N t E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E t E _

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b d 2. , 0 0 1 T. . 0 v. 7 u o . 3 3 3 3 2 i 2 2 _

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2 3 5 5 2 3 3 5 5 5 5 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 O N 4 2

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0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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i N0 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 O S c

. 1 1 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 l 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 N -

O CaC 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 I

T A 6 6 6 6 6 6 6 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 m 0

L 9 N

- 0 0 0 0 0 0 0 0 0- 0 - -0 - 0 - 0 - -0 0 0 0 0 0 0 0 0 i U E E E E E E- E E-E E- - - - - E E E E E E E E E E E E E E E E E E E E E L O 5 5 8 2 6 0 0 8 6 8 0 4 8 6 5 1 1 1 0 4 2 1 9 5 8 5 5 8 2 6 0 C. 3 4 1 0 9 0 2 1 8 1 1 5 4 8 6 8 3 1 2 5 1 9 8 0 3 8 4 1 0 9 0 .

t C 5 4 3 2 0 0 1 3 5 9 3 7 2 7 3 9 6 3 0 T.

5 2 0 9 7 5 4 3 2 0 0 u A R 1 1 1 1 1 1 9 8 7 6 6 5 5 4 4 3 3 3 3 2 2 2 2 1 1 1 1 1 1 1 1 l

e C A B

g m

s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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/ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

X iv 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 O 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 troptin s

3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 91 9 9 9 9 9 9 91 9 19 1 1 1 1 s t a 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 n

a ua t 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 O r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 R Tf l 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 A im c 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 r

E he oo . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 O -

L pR 1 uCU 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 s 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 olor 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 -

t mt n 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A o 6 6 6 6 6 6 7 7 T 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 - 7 7 7 .

C - 0 0 G 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 m 0 - E E E E E E E E E E E E E E E E E0 4E2 E E E9 5E8 E

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - i EEEEEEL hN t E E c - 5 5 8 2 6 0 0 8 6 8 01 4 8 615 1 1 1 1 5 5 8 2 6 0 egl e 8 4 1 0 9 0 2 8 1 5 4 8 6 8 1 7

1 2 5 1 9 8 0 3 8 4 1 0 9 0 .

5 4 3

. i 6..3 303 72 252 22 10 9 7 5 4 3 2 0 0 we 9

3 t

om i 12 0 0 1 9 3 s T5n 9 3o'2 5 7 t

C $ O l 1 1 1 t e 1 1 i 1 1 1 1 B

(c>u NUCLEA# CALCULATION SHEET l

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev No , Sheet No.

Code - Control Room Habitability C 1101826-E540 020 0 24 of f E I l

APPENDIX D DR. RAMSDELL CORRESPONDENCE I

I 1

0 e

(suu NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C.1101 826.E540-020 0 25 of f b To: Kenneth G Boughton ec:

Subject:

Re: ARCON96 1 don't think it would be appropriate for me to enter into a formal contractual relationship with GPU that involves providing guidance in the use of ARCON94 related to specific licensing actions. However,I would be happy to answer technical questions about the code and ,

underlying assumptions.

The data set that was used to develop ARCON includes concentration measurements that are within 10 m of the release point, and the mathematical formulations are continuous in the vicinity of the release point.

However, I'm not sure that I would try to use ARCON94 to estimate concentrations at 2 m, because when i I looked at the predicted and observed concentrations, some of the farthest outliers (model overprediction) I occurred for the samplers closest to the release point. On the other hand,I don't know of any models that are any better than ARCON94 for estimating concentrations at 2 m. ,

Reply Separator

Subject:

ARCON94 Author: kboughtonggpu.com at -SMTPLink Date: 1/22/98 8:43 AM Dear Mr. Ramsdell GPU Nuclear has been requested by recent NRC activities to re-evaluate the Three Mile Island Station -

' Uniti Control Room Habitability with respect to thyroid dose.

Previous licensing basis exempted the station from a thyroid dose evaluation pending commission evaluation of revised source term analysis and rule making. For more than 10 years this effort has proceeded slowly with only recent efforts through pilot programs. TMl is not within a pilot program and must per commission direction provide a thyroid analysis using traditional TID source term.

GPU's effort in responding to the activity has made use of the ARCON94 code for establishing X/Q values.

Our request to you is several fold.

Can you and will you provide technical service for the purposes of performing design verification of GPU's use of the ARCON96 code?

If yes, a proposalis required with your attached resume.

U

(c>u NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transpon X/Q 's Using ARCON96 Calc. No. Rev No Sheet No.

Code - Control Room Habitability C-1101-826-E5404)20 0 26 of fL Are you available to aid in use of the code with respect to the stabjective determination of diffuse area and resulting initial diffusion coefficients?

Is the code applicable for intakes located 5 feet from a leaking containment? Your work and collection of field data seems to address minimum distances at about 6 meters.

Your response is greatly appreciated.

Very truly yours, Ken Boughton kboughton@gpu.com 973-316 7054 1

l 4

(apu NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q *s Usmg ARCON96 Calc. No. Rev No Sheet No Code - Control Room Habitability C 1101-826-E540-020 0 27 of %

To: Kenneth G Boughton cc:

Subject:

Re[2): ARCON96 initial diffusion coefficients were added to ARCON96 to provide a method for approximating area (diffuse) l sources. As a result, the initial coefficients should be related to the dimensions of the area source. Initial l diffusion coefficients are not intended for use in enhancing the dispersion from point sources beyond the enhancement pmvided by the wake dispersion modelin ARCON96. Therefore,it would not be reasonable to attempt to define them on the basis of upwind building dimensions.

Van Reply Separator l

Subject:

Re: ARCON96 l Author: kboughtonggpu.com at -SMTPLink Date: 1/26/96 7:44 AM Thank you for your timely response and information provided relative to the close distance.

I have one additional question and it is concerned with the subjective part of applying ARCON06 for determining initial diffusion coefficients. For diffuse area sources, is it appropriate to consider adjacent building areas in addition to the containment area assumed to be leaking? The guidance examples l conservatively use exposed area (projected or cross sectional area) in determining initial diffusion coefficients. The concept is based upon a " virtual point source".

It is conceivable that additional blockage area by adjacent buildings and structures yielding a larger wake effect could produce higherinitial diffusion coefficients. Do you have any guidance on this? I am not a meteorologist and I am trying to understand the practicallimits associated with determining initial diffusion coefficients. The NRC position appears to be very conservative in this area (i.e. containment !

cross sectional area only).

kboughton@gpu.com

(c>u NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transpon X/Q 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C 1101826-E540-020 0 28 of f 2_.

To: Kenneth G Boughton ec:

Subject:

RE: ARCON96 1 don't think I would try to calculate X/Q at a receptor 2 m downwind from a diffuse source using ARCON96.

At least, I don't think I would go about trying to use a single release location and initial sigmas...

Van Original Message-From: kboughton@gpu.com [SMTP:kboughton@gpu.com)

Sent: Monday, February 23,1998 8:57 AM To: Ramsdell, James V Jr (Van)

Subject:

RE: ARCON96 ff I assume initial diffusion coefficients at zero, then X/Q's are about an order of magnitude higher (i.e. 4E-03). We are attempting to model a diffuse containment leak and the resulting consequences at an intake at 2 m from the adjacent containment building.

The building projected cross sectional area is 2127 m^2. The containment diameter is 43.1 m and the height is 51.3 m. I hava been using initial Sigma y at 10 m (43.1/4.3) and initial Sigma z at 25.65 m (51.3/2). Is this correct for a diffuse leak approximation? The met data is low wind speed with approximate average speeds at 1.6 m/s (5%),2.0 m/s (10%),2.7 m/s (20 %), and 4.5 m/s (40%).

Thanks againt Ken

(apu NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev No . Sheet No Code - Control Room Habitability C 1101-826-E540-n20 0 29 or 9 2 van.ramsdeil@pnl. gov on 02/23/9810:49:00 AM To: Kenneth G Boughton cc:

Subject:

RE: ARCON96 The data you refer to were collected by samplers that were not arranged in a sufficiently dense array to be able to make any statement about position of the measurements relative to the plume center line.

When I compared model predictions with the data collected on/near building surfaces, the model over-predicted concentrations about 95% of the time.

I suspect that many of the over-predictions are because measurements were not made at the plume center 11ne. ;

I haven't run ARCON96 recently, but X/Q of ?E-4 for a distance of 6 m seem extremely low. I would expect values of the order of 1E 2. I willlook at ARCON(^ when i get a chance. {

Van Original Message-From: kboughtor@gpu.com [SMTP:kboughton@gpu.com)

Sent: Monday, February 23,1998 9:12 AM To: Ramsdell, James V Jr (Van)

Subject:

Re: ARCON94 Dr. Ramsdell, Your e-mail of 1/23/98 has raised some additional questions using ARCON96 at the subject 2 m point /

receptor distance. Your response indicated that the model overpredicted X/Q values at short distances.

I am not sure i fully understand this statement when I review some of the field data presented in NUREGICR

- 5056 Appendix D. Data on page D.6 for Rancho Seco for Stability 1 and 6 indicate values in the magnitude of 3E-03 and 4E 03 sect m^3 for distances at about 6 m.

When I use ARCON961 get values on the order of 4E-04 sect m^3.

Does ARCON96 generally predict higher X/Q values for on or near building surfaces than would be expected by field measurements? Am i taking data out of context? .

l Your guidance is appreciated, thanks.

1 l

Ken 973 316-7054 I

($PU NUCLEA# CALCULATION SHEET

Subject:

Atmospheric Transport X/Q 's Using ARCON96 Calc. No. Rev.No . Sheet No.

Code - Control Room Habitabihty C-1101-826 E540-020 0 10 nr 92 APPENDIX E EXPANDED OUTPUT FILES YARD X/Q'S TMlYARD.OUT (TMlYARD. ZIP)

)

1

(c>u NUCLEA# CALCULATION SHEET l

i

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev.No Sheet No.

. Code - Control Room Habitability C 1101-826-E540-020 0 3 or 9 L j 1

APPENDlX F 1996 MET DATA QA i

i I

1 I

l l

l

(c>u NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport X/Q 's Using ARCON96 Calc. No. Rev No Sheet No.

Code - Control Room Habitability C.1101826-E540 n20 0 32 of f2 Oilality Assiirance Aspects:

Meteorological Data Three Mile Island Nuclear Generating Station RE: TMl Control Room Habitability Study The following regulatory guidance is required for a nuclear meteorological program to provide data needed to estimate potential radiation doses to the public as a result of the routme or accidental release of radioacuve matenals to the atmosphere and to assess other environmental effects: ,

US N RC Safety Guide 23 - desenbes instrument accuracy, maintenance and service scheduling and reducuon and compilation.

Instrument redundancy is required at potential elliuent release height.

INSTRUMENTATION FOR LIGHT WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS DURLNG AND FOLLOWING AN ACCIDENT- USNRC Rev Guide 1.97-desenbes the vanous mstrument ranges acceptable. Ranges for honzontal wind speed, direcuon and the determmauon of stability are included.

Quality Assurance Atmosphene monitonng is a process greatly affected by external iruluences (weather, mechanic, etc.). When one needs to discover how much vanability in a process is due to random vanation and how much is due to unique events / individual actions m order to determme whether a process is in statistical control, the use of a statisucal Control Chart is employ ed. This analytical statistical method applies when analysis is performed over time. Basically, as ume goes on, mstrumentauon can malfunction.

The Control Chart is simply a run chart with statisucally determined upper and lower control Imuts drawn on either side of the process average. If the process exceeds the controllinuts (usually bsigma), it could indicate a problem with a parucular instrument. Also, if the process is consistently on "one side" of the average, this could mdicate that mstrument performance is degrading.

The meteorological data from TMI and Oyster Creek are not only reviewed on a 15-mmute basis (for the previous dan but redundant sensors undergo the aforementioned stausucal analysis to ensure proper data are used in offsite (and onsitei air dispersion analysis, both routine and non-routine. As previously mentioned, redundant mstrumentation are required at heights of potential radiological release (stacks, vents, etc.).

In addition, w hen the instmment signal is received from the sensor to the tower PC, all data are passed through software that will flag

" bad" data points or tf a parucular readmg is consistent over a long penod of time, the softv.are will tag it as " questionable" 1996 TMl Meteorological Data 1

l The information provided has undergone quality assurance on a daily basis (15-minute scan of previous day) as well as 1

i monthly runnina statistical control charts. The latter ensured that no develocing malfunction occurred m any senscr that I would make the meteorological data non-representative of a potential radioactive release point. The dataset. I i

l

(c>u NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transport YJQ 's Using ARCON96 Calc. No. Rev.No. Sheet No.

Code - Control Room Habitability C.I 101-826-E540-020 0 33 or f 7

'ALL1996.TMI.WEAYHER. DATA

located in the TSO mainframe in Reading was simply extracted and placed in a format that would allow the user to perforTn Control Room Habrtability air dispersion assessment, that is, no further changes to '

the data were made.

i i,

l

(c>u NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transpon X/Q 's Using ARCON96 Calc. No. Rev No . Sheet No.

I Code - Control Room Habitability C-1101-826 E540-020 0 14 or 9 7 APPENDIX G PLG LETTER MET DATA I 4

O e

1 e

(apu NUCLEAR CALCULATION SHEET

Subject:

Atmosphenc Transpon X/Q s Using ARCON96 Calc. No. Rev.No. . Sheet No.

Code - Control Room Habitability C 1101826-E540-020 0 35 of 9 2.-

March 2,1998 Mr. Ken Boughton GPU Nuclear Corporation 100 Interpace Parkway Parsippany, NJ 07054

Dear Ken:

PLG has completed the review of TMI meteorological data for the periods of 1976,78 and 1980-82. All of'the available data for those periods have been e-mailed to you in an AScil format. The data for these years has beert cdited by a meteorologist familiar with the TMl area meteorology. Periods of questionable or bad data were identified and checked against redundant sensors or other levels on the tower. If necessary data were compared with local National Weather Service stations. The bad data was coded so that it would not be used in any calculations. PLO has a data quality program controlled by our Meteorological Projects Policies and Procedures Manual (MPPPM) that is used in processing all meteorological data. A controlled copy of this manual (Copy Number 20)is maintained at GPU by Mr. Ronald Huddy in Parsippany, NJ.

The meteorological data collected at TMI utilizes an onsite Data Recording Terminal (DRT) computer to collect 15 minute averages of all meteorological parameters. The original" raw", unedited data was saved on tape and stored at PLO. The older years (before mid 1981) were stored on 7-track tapes which are no longer readable. In our records, we have found the following " raw" data tapes for the period of data used in your study:

1976 Not available 1978 Tapes 940,679 and 675 1980 Tapes 1143,1160,916 and 1176 1981 Tapes 1180 and 1313 1982 Tapes 1476 and 1119 Copies of the raw data from July 1981 through December 1982 have been sent to Mr. Paul Schwartz on diskettes.

If you have any questions about the meteorological data described above, please call Keith Woodard or me.

Very truly yours, i

Mark J. Abrams 1

Sheet 3G of 9 2

~

C-1101-826-E540-020 NUCLEAR VERIFICATION PLAN /

SUMMARY

SHEET (EP-006) l Item No, Metho@ Depth of Vertncation Required Req'd Compt. Date l 1 Verify the use of ARCON96 with the met files provided for determinlag X/Q's. Venfy the 3/6/98 assumptions and inputs are accurate, appropriate for use in the calculation, and are j used appropriately in the calculation. Given the input, assumptions, and methodology, venfy the results are accurate and appropriate. Document the results of verification summarizing scope, methods, results and conclusions, and complete the verification checklist. Assigned to K.Woodard. l I

2 Confirm the ARCON96 code satisfies the requirements of the GPUN

Computer 3/6/98 Program Control Procedure *,5000-ADM-7340.01, Rev. 6, EP-007. Assigned to R. J.

McGoey.

l l

Asagned Vwincabon Engineer Task 1: Keith Woodard - PLG, Inc. cuanned per 4 413 e O Yes S Waived Jusuncadon for Walver Attached memo E540-96-008, dated March 3,1998.

Assagned Venneadon Engineer Task 2: Richard J. McGoey ouahfied per 4 413 b a Yes O Waived l secton Manager (sM)(sagn) 'MQ % Date 1 3 q,g l )

Summary of venfication scope, methods, results and conclusic s.

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) Vfctc62 4- 1Etc g g ) $ G ty 'sc h N !kW5"{WWW 4 d M-d* 4W W ade.s0W24Lau.

A&NC5H% $. W QWcOocstedcel6A @'c9'Yubt2h. w e' On "yHHhte U 0/M kdL L i!'[44d coif 4he#ht22?Mui. M 42<:'@d'$ h C/k M.<d Based on this evaluation, the calculation is venfied to be acceptable.

Venncation Engineer (pnnt) d j7/f [g ppgg (,gn [ oate 1 ((*h J' Use additional sheets if necessary

(~* ll Cl

N le .- [fyo - o g y s 1 , y Y f.'

MM 37 of 96 -

Pr: gram

Title:

M00N 96.

Developed for: U.S. Nuclear Regulatory Commission

.Cffice of Nuclear Reactor Requiacion Divisitn of Reactor Program Management Date: June 25, 1997 11:00 a.m.

NRC Osntacts: J. Y. Lee Phones (301) 415 1080 e-mails fyllenec. gov J. J. Hayes Phones (301) 415 3167 e-mails $$henre. gov L. A Brown Phones (301) 415 1232 e-mails lan28nec. gov Code Developer J. V. Ramsdell Phone: (509) 372 6316 e-mails j,,ramsdellepnl. gov

. Code Documentations NUREG/CR-6331 Rev. 1

, The program was prepared for an agency of the United States Government. Neither the United States Gaw .nment nor any agency thereof, nor ,any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 3/ 6/1998 at 08:41:28 moa gye C s

....... nee,1,,,,..........

Number of Meteorological Data riles = 5 Meteorological Data rile Names MA,./ / N SM/g g tmimet16.are tmimet?8. arc tmimet90. arc D v4

(

tmimet81.are tmimet02. arc Height of lower wind instrument (m) = 30.5 Height of upper wind instrument (m) = 31.0 Wind speeds entered as meters /second Ground-level release Release height (m) = .0 .

l Butiding Area (m*2) = 2127.0 Effluent vertical velocity (m/s) = .00 Veat or stack flow (m*3/s) = .00 Vent or stack radius (m) = .00 Direction .. intake to source (dog) = 049 ,

Wind direction sector width (dog) = 90 i Wind direction window (dog) = 004 - 094 Distance to intake (m) = 91.4 I Intake height (m) = 3.7 l Terrain elevation difference (m) = .0 ]

Cutput file names tm15yr44. log

.tm15yc44.cfd 4

Minimum Wind Speed (m/s) = .5 Surface roughness length-(m) = .10 Sector averaging constant = 4.0 ;

Initial value of signa y = 10.00 l Initial value of sigma a = 44.00 Expanded output for code testing not selected

C.-ilo - 72 G - 25V3 - ose D+ C T 31 af 9 R Total nuxter of hours of data processed = 43048 Hours of missing data = 2130 Hours direction in window = 5357 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 3752 Hours direction not in window or calm = 32601 DISTRIBUTION '

SUMMARY

OATA BY AVERAOING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 120 UPPER LIM. 1.CCE-03 1.00E-03 1.0CE-03 1.00E-03 1.0CE-04 1.00E-04 1.00E-04 1.00E-04 1.0CE-04 1.00E-04 LOW LIM. 1.CCE 1.0CE-07 1.00E-07 1.00E-07 1.00E-08 1.00E-08 1.00E-08 1.00E-08 1.00E-08 1.00E-08 ABOVE RANGE 0. O. O. O. O. O. O.

O. O. Q.

IN RANGE 9109, 12432, 16240. 20649, 24875. 30795. 37190.

38084. 37621, 38557 BELOW RANOE 0. 0. C. O. O. O. O.

O. O. O.

ZERO 32601, 28970. 24592. 19149. 15834. 9063. 635.

25. O. O.

TOTAL X/Qs 41710, 41402. 40832. 39798. 40709. 39858. 37825.

38109. 37621. 38557 4 NON IERO 21.84 30.03 39.77 51.88 61.10 77.26 98.32 99.93 100.00 100.00 95th PERCENTILE X/Q VALUES 1.15E-04 1.12E-04 9.12E-05 8.54E-05 6.79E-05 4.75E-05 2.97E-05 2.62C-05 2.35E-05 2.13E-05 956 X/Q for standard averaging intervals Gh h O to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months th&-

1.15E-04 ),Tg4 2

8 to to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 24 hours 7.54E-05 2.85E-05 QM h',lg/g,-I, 1 to 4 days 2.37E-05 '2s , f,g g. $

4 to 30 days 2.0CE-05 :k p A , $'

HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.14E-04 1.81E-05 SECTOR-AVERAGE 7.13E-05 1.13E-05 NCRMAL PROGRAM COMPLETION

h $ # W h b&&b &

useof f -tla deuAnd lu&g4f-k rki&A widef c,iqu w . % uaw'd /u 4pG/ u'uc.2 fa'^Ler jur.gighsig &&-l g2 Arm M10 $ iktEans t%ww"m M5W h /A4 isle % $ ucl h Y W '"M N0% #*

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c. - o. i - ma s - s .5 o -ed 21+9 6T 38) d- 9'2_.

l

.1.905E-06 9109. 12432. 16240. 20649. 1.905E-06 24875. 30795. 37190. 38084. 37621. 38557.

1.130E-06 9109. 12432..16240. 20649. 1.738E-06 24875. 30795. 37190. 38084. 37621. 3e557 1.585E-06 9109. 12432. 16240. 20649. 1.585E-06 24875. 30795. 37190. 38084. 37621. 38557, 1.445E-06 9109. 12432. 16240 20649. 1.445E-06 24875. 30795, 37190. 38084. 37621. 38557 1.318E-06 9109. 12432. 16240. 20649. 1.31st.06 24879 307 *L 3?190. 38094. S'8?t. '*??'. !

1.202E-06 9109. 12432. 16240. 20649. 1.202E-06 24875. 30795. 37190. 38C84. 37621. 33557 1.096E-06 9109. 12432. 16240. 20649. 1.096E-06 24875. 30195. 37190. 38084. 37621. 38557 I 1.000E-06 9109. 12432. 16240. 20649. 1.000E-06 24875. 30795. 37190. 38084. 37621. 38557 i 9.120E-07 9109. 12432. 16240. 20649. 9.120E-07 24875. 30795. 37190. 38084. 37621. 38557

'8.318E-07 9109. 12432. 16240. 20649. 8.318E-07 24875. 30795. 37190. 38084. 37621. 38557 7.586E-07 9109. 12432. 16240, 20649. 7.586E-07 24875. 30795. 37190. 38084. 37621. 38557 6.918E-07 9109. 12432. 16240. 20649. 6.918E-07 24875. 30795. 37190. 38084. 37621. 38557 6.310E-07 9109. 12432. 16240. 20649. 6.310E-07 24875. 30795. 37190. 38084. 37621. 38557 5.754E-07 9109. 12432. 16240. 20649. 5.754E-07 24875. 30795. 37190. 38084. 37621. 38557 5.240E-07 9109. 12432. 16240. 20649. 5.248E-07 24875. 30795. 37190. 38084. 37621. 38557 4.786E-07 9109. 12432. 16240. 20649. 4.786E-07 24875. 30795. 37190. 38084. 37621. 38557 4.365E-07 9109. 12432. 16240. 20649. 4.365E-07 24875. 30795. 37190. 38084 37621. 38557 3.981E-07 9109. 12432. 16240. 20649, 3.981E-07 24875. 30795. 37190. 38084. 37621. 38557, 3.631E-07. 9109. 12432. 16240. 20649. 3.631E-07 24875. 30195. 37190. 38084. 37621. 38557, 3.311E-07 9109. 12432. 16240. 20649. 3.311E-07 24875. 30795. 37190. 38084. 37621, 38557, 3.020E-07 9109. 12432. 16240. 20649. 3.020E-07 24875. 30195. 37190. 30084. 37621, 38557 2.754E-07 9109. 12432. 16240. 20649. 2.754E-07 24875. 30795. 37190. 30084. 37621. 38557 2.512E-07 9109. 12432. 16240. 20649. 2.512E-07 24875. 30795. 37190. 38084. 37621. 38557 2.291E-07 9109. 12432. 16240. 20649. 2.291E-07 24875. 30795. 37190. 38084. 37621. 38557 2.089E-07 9109. 12432. 16240, 20649, 2.089E-07 24875. 30795. 37190. 38084. 37621. 38557.

.1.905E-07 9109.'12432, 16240. 20649. 1.905E-07 24815. 30795. 37190. 38084. 37621, 38557 1.138E-07 9109. 12432. 16240. 20649. 1.738E-07 24875. 30795. 31190. 30084. 37621, 38557 1.585E-07 9109. 12432. 16240. 20649. 1.585E-07 24875. 30795. 37190. 38084. 37621. 38557 1.445E-07 9109. 12432. 16240. 20649. 1.445E-07 24875. 30795. 37190. 38084. 37621. 38557 1.318E-07 9109. 12432. 16240. 20649, 1.318E-07 24875. 30795. 37190. 38084. 37621. 38557 1.202E-07 9109. 12432. 16240. 20649. 1.202E-07 24875. 30795.- 37190. 38084. 37621. 38557 1.096E-07 9109. 12432. 16240. 20649. 1.096E-07 24875. 30795. 37190. 38084. 37621. 38557 1.000E-07 9109. 12432. 16240, 20649. 1.000E-07 24875. 30795. 37190. 30084. 31621. 38557.

Belw. Lim. O. O. O. O. Belw. Lim. O. O. O. O. O. O.

g.

e n

. _ _ _ _ __.____.-_5

o C.-- \\o w 8.1& Esto - o a o ufET yo 4 92 X/Q 0".!MU1.ATIVE FREQUENCY DISTRIB0"TIONS X0Q 1 2 4 8 XOG 1? 24 96 168 360 ??S

~ ADv.' Lim. O. O. C. O. ADv. Lim. C. C. 0. O. O. O.

9.120E-04 0 .' O. O. O. 9.1201-04 170. 0. O. Q. O. O.

8.319E-04 0 .- 0. O. O. 8.318E-04 616. O. O. O. 0. . O.

7.596E-04 0. O. c. C. 7.586E-04 1202. 74. O. O. O. O.

6.918E-04 0. O. -0. O. 6.918E-04 1860. 270. O. C. O. O.

6.310E-04 0. O. C. O. 6.310E-04 2684. 541. 13. O. 0. O.

5.754E-04 3. 3. O. O. 5.754E-04 3574. 847 32. O. O. 0, 5.248E-04 c. O. -0. O. 5.248E-04 4572. 1293. 82. O. O. 0.

4.796E-04 0. O. O. O. 4.786E-04 5515. 1915. 141. O. O. O.

4.365E-04 0. O. O. O. 4.365E-04 6658, 2735, 221. 25. O. O.

3.981E-04 0. O. O. 0. 3.981E-04 7723. 3747 438. 100. .0. C.

3.631E-04 0. O. O. O. 3.631E-04 8974. 4946. 147. 205. O. O.

3.311C 0. O. O. O. 3.311E-04 9901. 6225. 1125, 485. O. O.

3.020E-04 0. O. O. O. 3.020E-04 10775. 7709. 1492. 871. 125. O.

2.754E-04 0. O. O. O. 2.754E-04 12000. 9188. 2674. 1454. 399. O.

2.512E-04 0. O. O. O. 2.512E-04 12869. 10630. 4048. 2284. 1151. 30.

2.291E-04 0. O. O. O. 2.291E-04 13823. 12167 5838. 3601. 2129. 749.

2.089E-04 0. O. O. O. 2.089E-04 14470. 13408. 8005. 5747. 3390. '2240.

'1.90$E-04 0. O. O. o 0. 1.905E-04 14928. 14840. 10264. 8254. 5640, 4367 1.738E O. O. 0. 0. 1.738E-04 16196. 16272. 12491. 10981. 8780. 8176.

't.585E-04 0. 3. O. O. 1.585E-04 17284. 17340. 14844. 14096. 12397 12391.

,-1.445E-04 0. O. O. O. 1.445E-04 18163. 18583. 16859. 17123. 16327, 16227 1.318E-04 0. O. O. O. 1.318E-04 18394. 19738. 18942. 19737. 20382. 20975.

1.202E-04 0. O. O. O. ~1.202E-04 18582. 20400. 21021. 22161. 23935. 26372.

1.096E-04 4525. 2602, 1010. 268. 1.096E-04 19496. 21433. 22993. 24335. 27050. 30547 1.000E-04 6548. 3770. 1634. 521. 1.000E-04 19753. 22074. 24689. 26399. 29411. 32978.

9.120E-05 7287 4321, 2038, 1295. 9.120E-05 21351. .22814. 26180. 28385. 31340. 34172.

8.318E-05 1622. 4654. 3824. 2254. 8.318E-05 22120. 24156. 21536, 30144. 32889. 35201.

7.586E-05 1802. 4826. 4758. 2858. 7.586E-05 22365. 24667. 28829. 31688. 33879. 36086.

6.918E-05 8222. 5105. 5203. 4104. 6.918E-05 22463. 25106. 30151. 33055, 34640. 36888.

6.310E-05 0413. $195. 5433. 4758. 6.31C*-05 22562. 25237 31174. 33957 35372. 37418.

5.754E-05 8550. 5282. 5572. 5067. 5. 7 54f>05 23705. 26252, 32002. 34864. 36315. 31664.

5.248E-05 8600. 10230. 8760. 6986. 5.248E-05 24308. 26724. 32664. 35522. 36819. 38128.

4.786E-05 8796. 10901. 9234. 7457 4.786E-05 24484. 26862. 33502. 35961. 37079. 38331.

4.365E-35 8868, 11247 9537. 7732. 4.365E-05 24576. 27865. 34100. 36308. 37142. 38365.

3.981E-05 8955, 11386. 9734. 10021, 3.981E-05 24629. 20092. 34415. 36623. 37211. 38551, 3.631E-05 9004. 11558. 9882. 10549. 3.631E-05 24691. 20202. 34983. 36913. 37343. 38557 3.311E-05 9040. 11781. 10015. 10895. 3.311E-05 24754. 28235. 35350. 37059. 37370, 38557 3.020E-05 9057. 11970. 10109. 11072. 3.020E-05 24788. 20432. 35478. 37158. 37427 38557 2.754E-05 9080. 12069. 13171. 13286. 2.754E-05 24009. 30022. 35925. 37190. 37484. 38557, 2.512E-05 9093. 12152, 14661. 14327. 2.512E-05 24817 30330. 36090, 37361. 37498. 38557.

2.291E-05 9099. 12251, 15013. 14615. 2.291E-05 24837 30486. 36127 37466. 37511. 38557.

2.089E-05 9107 12298. 15198. 14953. 2.089E-05 24852. 30526. 36317, 37546. 37544. 38557 1.905E-05 9;07. 12357 15280. 15120. 1.905E-05 24864. 30582. 36349. 37611 37541 36557 1.738E-05 3109. 12384. 15476. 15230. 1.738E-05 24868. 30667 36389. 37622. 31558. 38557.

1.585E-05 9109. 12392. 15716. 15350. 1.585E-05 24871. 30707 36401. 37680. 37559. 38557.

1.445E-05 9109. 12406. 15874. 15422. 1.445E-05 24872. 30726. 36567. 37689. 37561. 38557 1.318E-05 9109. 12415. 15960. 18989. 1.318E-05 24872. 30736. 36733. 37697 37562. 38557 1.202E-05 9109. 12419. 16024. 19508. 1.202E-05 24812. 30757. 36118. 37715. 37563. 38557

. 1.096E-05 9109. 12427, 16088. 19774. 1.096E-05 24875. 30763. 36821. 31746. 37581. 38557.

1.000E-05 9109. 12431. 16144. 19858 1.000E-05 24815. 30719. 36837. 37755. 37581. 38557 3.12 E-06 9109. 12432. 16178. 19916. 9.120E-06 24815. 33792. 36840. 37756. 37584. 38557 8.318E-06 9109. 12432. 16197. 20189. 8.318E-06 24875. 30794. 36840. 37769. 37584. 38557 7.586E-06 9109. 12432. 16201. 20350. 7.586E-06 '24875. 30795. 36865. 37833. 37584. 38557 6.918E-06 9109. 12432. 16218. 20402. 6.918E-06 24815. 30795. 37056. 37853. 37591. 38557 6.310E-06 9109. 12432. 16224. 20460. 6.310E-06 24875. 30795. 37119. 37861. 37592. .38557 5.754E-06 9109. 12432. 16227. 20522. 5.754E-06 24875. 30795. 37121. 37861. 37592. 38557 5.248E-06 3109. 12432. 16240, 20550. 5.248E-06 24875. 30195. 37121. 37861. 37594. 38557 4.786E-06 9109. 12432. 16240. 20588. 4.786E 06 24875. 30795, 37163. 37861. 37594. 38557.

4.365E-06 9109.-12432. 16240. 20618, 4.365E-06 24815. - 30795. 37190. 37925. 37594. 38557

.3.981E-06 9109. 12432. 16240. 20623. 3.981E-06 24875. 30195. 37190. 38047 37594. 38557

3. 6 3' t-06 9109. 12432. 16240. 20634, 3.631E-06 24875. 30795. 37190. 30084. 37621. 38557

.3.311E-06 9109. 12432. 16240. 20638. 3.311E-06 24875. 30795. 37190. 38084. 37621. 38557 3.02:E-c6 9509. 12432, 16240. 20639. 3.020E-06 24875. 30795. 37190. 38084. 37621. 38557 2.754E-06 3109. 12432. 16240. 20646. 2.754E-06 24875. 30795. 31190. 38084. 37621. 38557

~2.512E-C6 9109. 12432. 16240. 20649. 2.512E-06 24875. 30195. 37190. 38084. 37621. 38557 2.291E-06 9109. 12432. 16240. 20649. 2.291E-06 24875. 30795. 37190. 38084. 37621, 38557 2.083C-C6 9139. 12432.-16240. 20649. 2.089E-06 24875. 30795, 37190. 38084. 37621. 39537

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(GUNUCLEAR subject: DESIGN VERIFICATION WAIVER Date: March 3,1998 FOR MR. KEITH WOODARD From: R. J. McGoey - Manager, Location: Morris Corp. Center Mechanical / Structural Engineering E540-98-008 To: File Ref.: Resume of Mr. Keith Woodard (attached)

This letter is the waiver of Responsible Technical Reviewer (RTR) requirement for Mr.

Keith Woodard to design verify GPUN Calculation C-1101 826-E540-020, Rev. O,

" Control Room Habitability Atmospheric Transport X/Q using ARCON 96 Code" l Mr. Woodard has 38 years of experience and is considered an expert in the subject of atmospheric transport also an expert on TMI atmospheric conditions which he has conducted numerous studies on that subject. The referenced resume for Mr. Woodard, which is also attached, summarizes his extensive experience. This experience, coupled with his demonstrated knowled8e, confirms he satisfies the criteria for design verification of Section 4.4.1 of GPUN Calculation Procedure 5000-ADM-7311.01 (EP 006) of being competent in the subject matter of the calculation, qualified to perform the work being verified and knowledgeable on the impact it may have on nuclear and radiological safety.

Mr. Woodard has also been independent of the preparation of the calculation. Mr.

Woodard is qualified to design verify this calculation.

R.%. McG Extension 7950 RJM\cc Attachments Cc: K. G. Boughton - Engineer, Mechanical / Structural Engineering i

i mmswuwmm j l

I

C.- H ei- 3 a 6 - Es* -oc ss+ee.T v3 J- 4 KEITH WOODARD

SUMMARY

Vice President, Washington, DC Area Office and senior engineer with PLG. Thiny-three years of experience in atmospheric dispersion modeling and analysis, radionuclide and chemical dose assessment / reconstruction, and probabilistic risk assessment. Has been directly involved in meteorological data collection and analysis, dispersion assessments, dose calculations, and emergency planning at more than half of the U. S. commercial nuclear power plant sites and at U.S. National Laboratories.

EDUCATION: Graduate Courses in Reactor Design and Safety Analysis, Catholic University, Washington, D.C., 1966-1967 Certificate, International Institute of Nuclear Science and Engineering, Argonne National Laboratories,1964 M.S., Nuclear Engineering, University of California at Los 'N Angeles,1963 B. A., Physics, Occidental College,1961 RECENT EXPERIENCE: Responsible for development and continuous support of the computerized Meteorological Information and Dose Assessment System (MIDAS) used in support of emergency planning, training, and response at more than 30 U.S. nuclear plant sites. Directed development of the chemical version of MIDAS to include assessment of chemical spills for use by the chemical process industry to support emergency planning activities at more than 35 facilities.

Continues to serve as an expert witness in support of the ongoing ,

legal process following the Three Mile Island Unit 2 accident. I Immediately following the accident, became involved in assessing l i

the radiation exposure in the vicinity of the plant. Working as the utility representative, developed computer models to reconstruct the fission product release source term using environmental measurements and site meteorological data.

Responsible for developing the first site-specific model (CRACIT program) to assess reactor accident consequences, which has been used in probabilistic risk assessments for more than 12 plants.

Directed development of the CRACEZ consequence model, which incorporates three dimensional wind fields, a complex evacuation dose model, and time-dependent releases.

. 1

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. 5M a r W eF yt--

OTHER EXPERIENCE: Extensive involvement in the development of radiological accident

, consequence codes, which required working closely with many representatives from nuclear utilities and the U.S. National Laboratories. Directly involved in dose assessment for the DOE High Flux Isotope Reactor facility at Oak Ridge National Laboratory. Developed site-specific consequence model for use at Rocky Flats. Project manager for installation of computerized on-line emergency dose assessment models at Los Alamos National Laboratory including both radiological and chemical versions of MIDAS. Served as co-chairman of DOE committee to review chemical dispersion computer models and made recommendations regarding best practices.

Responsible for developing computer models using probabilistic methods to determine atmospheric dispersion factors and accident doses for use in safety evaluations of nuclear plants and chemical process facilities. Developed models for establishing environmental monitoring programs and for plant siting evaluations. Directly I responsible for supervising atmospheric dispersion analyses in )

support of more than 40 applications for approval of power i-!ar.:

sites and licenses, for operation and control of more than 16 weather towers, for 2 major atmospheric dispersion field experiments, and for other field measurement programs.

Responsible for developing computer models to assess environmental effects of cooling tower operations.

Was an active participant in the International Comparison Study of Reactor Accident Consequence Models (benchmark study) conducted by the Organization for Economic Cooperation and Development, and recently chaired an IAEA workshop on accident consequences. .

Left the U.S. Atomic Energy Commission (AEC)in 1967 to join PLG. From 1963 to 1967 worked as a project leader in the AEC's

. Division of Reactor Licensing responsible for analysis and evaluation of nuclear safety aspects of power and research reactors.

MEMBERSHIPS: American Nuclear Society

)

l woodartren 039/2.'IE 98

C,- M -vate - Es'4e -,go 1%0s W ' of 9 'L. -

PUBLICATIONS .

Woodard, K., M. J. Abrams, J. Lewis, T. J. Celi, M. J. Pine, "Using Offsite Measurements to Estimate Doses from Unmonitored Source Terms," presented at the ANS Sixth Topical Meeting on Emergency Preparedness and Response, April 1997. .

Carbone, J. P., W. C. Gekler, C. M. Roy, K. Woodard, " Control Room Habitability During' Releases of Toxic Substances," January 1996.

Woodard K., M. J. Abrams, and J. Lewis, " Resolution ofIssues Related to Implementation of EPA 400 in Dose Assessment Models," presented at the ANS Sth Topical Meeting on Emergency Preparedneu and Response, April 1995.

Abrams M. J. and K. Woodard, " Enhanced Distribution ofInformation Via Networks to Suppon Emergency Response Activities," presented at the ANS Sth Topical Meeting on Emergency . .

Preparedness and Response, April 1995.

Abrams, M. J. and K. Woodard, " Remote Sensing and Automatic Dispersion Modeling,"

presented at Envirosoft '92, Ashurst, Southhampton, UK, September 1992.

Beychok, M. R., T. E. Fenstermacher, W. R. Fuller, W. C. Gekler, R. W. Myers, and K. Woodard, "Offsite Cosequence Analysis for Rh6ne-Poulenc Basic Chemicals Co. Maninez Plant," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG 0839, l September 1991.

1 Woodard, K., M. R. Beychok, T. E. Fenstermacher, W. R. Fuller, and W. C. Gekler, "Offsite Consequence Analysis for Rh6ne-Poulenc Basic Chemicals Co.," PLG, Inc., prepared for Stone &

Webster Engineering Corporation, PLG-0795, February 1991.

Woodard, K., T. E. Fenstermacher, W. R. Fuller, and W. C. Gekler, "Otisite Cosequence Analysis for Rh6ne-Poulenc Dominguez Plant," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG-0794, November 1990.

Woodard, K., M. R. Beychok, T. E. Fenstermacher, W. R. Fuller, and W. C. Gekler, "Offsite

. Consequence Analysis for Tosco Avon RMPP," PLG, Inc., prepared for Stone & Webster Engineering Corporation, PLG-0791, November 1990.

Woodard, K., T, E. Fenseanacher, and J. Lewis, "The CRACEZ Radiological Consequence j Model (with Improved Modeling of Dispersion and Evacuation)," 1990.

Woodard, K., T. El Fenstermacher, and N: Addison (Do.w), "A Quick Running Personal Computer Model for the Evaporation and Dispersion of Dense Gases," presented at the l International Conference of Vapor Cloud Modeling, November 1987. i i

Woodard, K., J. Lewis,' and T. E. Fenstermacher, "Using the CRACIT Consequence Mode for Determining Spatial Risk to Support Emergency Planning," presented at the PSA '87 Conference, Zurich, Switzerland, September 1987. l Woodard, K., "The Enhanced CRACIT Computer Code and Insights Gained from Its Use," !

~

. I woodard.rm039415,98 j

c.-tion - t % - Esw -o ao Swear We eF f1 presented to the Technical Committee on Computer Codes for the Probabilistic Assessment of Accident Consequences (IAEA), June 1987.

Woodard, K., "A Touch Screen Man-Machine Interface for Emergency Dose Calculations,"

presented at the ANS Winter Meeting, Los Angeles, California,1987.

Woodard, K., J. Lewis, and M. Abrams, " Computer Trends in Accident Assessment and Routine Data Collection," presented at the HAZMAT '86 Conference, June 1986.

Woodard, K., "Real-Time Microcomputer-Based Dose Computations Using a Three-Dimensional Particle Tracking Dispersion Model in MIDAS," presented at the Workshop on Real-Time Computing of Environmental Consequence of a Accident Release to AtmeWe from a Nuclear Installation, Luxembourg, September 1985.

Woodard, K., " Sensitivity of Consequence Results to More Sophisticated Atmospheric Dispersion and Other Modeling Enhancements," presented at the Workshop on Reactor Accident Off-Site Consequence Modeling Assessment and Application, Tokai, Japan, April 1984.

Woodard, K., "Use of the CRACIT Consequence Mode for Real-Time Accident Dose Assessment," presented a the Workshop on Reactor Accident Off Site Consequence Modeling Assessment and Application, Tokai, Japan, April 1984.

Woodard, K., and M. Abrams, " Current Trends in Minicomputer-Based Near-Real-Time Reactor Accident Consequence Predictions," presented at the American Nuclear Society W'mter Meeting, Washington, D.C., November 14-19, 1982.

Woodard, K., and T. E. Potter, " Consideration of Source Term in Relation to Emergency Planning Requirements," presented at the Workshop on Technical Factors Relating Impacts from Reactor Releases to Emergency Planning, Bethesda, Maryland, January 12-13, 1982.

Alpert, D. J., P. H. Gudiksen, and K. Woodard, "Modeling Atmospheric Dispersion for Reactor Accident Consequence Evaluation," presented at the International ANS/ ENS Topical Meeting on Probabilistic Risk Assessment, Port Chester, New York, September 20-24,1981.

Woodard, K., and T. E. Potter, " Assessment of Noble Gas Releases from the Three Mile Island Unit 2 Accident," presented at the American Nuclear Society 25th Winter Meeting, San Francisco, California, November I l-15,1979.

Woodard, K., and T. E. Potter, " Modification of the Reactor Safety Study Consequence Computer Program (CRAC) to Include Plume Trajectories," presented at the American Nuclear Society 25th Winter Meeting, San Francisco, Califomia, November 11-15, 1979.

Woodard, K., and T. E. Potter, " Selecting Probability for Use in Direction Dependent Accident Dispersion Models Consistent with Past NRC Practice," Transactions of the American Nuclear Society, Vol. 26, June 1977.

Woodard, K., and T. E. Potter, "Probabilistic Prediction of X/Q for Routine Intermittent Gaseous Releases," Transactions of the American Nuclear Societv. Vol. 26, June 1977.

..xurer o39r2/is.9s a

C -I lo t - # 2(, - Er% -e 1.-

N8T 47 sf-jPt Woodard, K., " Feasibility of Using Richardson Number for Determining Atmospheric ;

Dispersion," Transactions of the American Nuclear Society 1974 Winter Meeting, Vol. 22, November 1975.

l Woodard, K., " Sensitivity of Atmospheric Diffusion Estimates to Meteorological Data Recovery l and Accuracy," Nuclear Technology, Vol. 25, April 1975. I Woodard, K., R. V. Calabrese, and J. Halitsky, " Prediction of Temperature and Moisture Distributions in Cooling Tower Plumes," presented at the Symposium on Atmospheric Diffusion and Air Pollution, sponsored by the American Meteorological Society, Santa Barb.ac.. California, ,

September 1974.

]

Woodard, K., " Probability Treatment of Atmospheric Dispersion for Dose Calculation," Nuclear Technology, Vol.12, November 1971. ,

1 I

4 I

I i

l woodard.res0394'l8 98

CALCULATION VERIFICATION CHECKLIST Sheet of O U tRev. Er.coe)

NUCLEAM cac. Tme Atmosphefic Transport X/Q's Using ARCON96 Code - Control calc. No. R ev.

Room Habitability C1101-826-E540-020 0 venacenon by-(Pnnt Name) Section Oste Keith Woodard, PLG Inc. PLG 3///fy Flece e check mark la the appecable hos (Yes, No, N/A) for each lease. 4 l

"NO" sney 8=d% the design er verternden le imeossplete regeertog a teek rquest be seeigned by the reopene&bie Section Mensger. 1 The Sectise Manager shes review eerk "NO" reopease te deternshis if Tank Regeses asess te he prepared. !

"N/A"(Not Appilcoble) dose not regadre any flerther orden by the VertScaden Engineer.

The Vertsemetee Sammanary (VS)(Eskihlt 7A) smay be need to estEme the Vertnemeiseragama*#s work or for cosneneste doenned appropropetete by the VertAresten Fmpaner.

Review Check ITEMS Desion Compliance Yes No N/A Demien Innad & Data - Were the inpute conectly selected, referenced (latest revoson) and incorporated into the caeculaeon? { l

[

Amaumations - Are assumptions necessary to perform the calculabon adequately desenbod and reasonable?

] ] I Reaulatory Ranuirements - Are the appilcable codes and standerde and regulatory requrements,incluchng leeue and g addende, property identified and ther requremente met? ]

Construction /Onaratina Emnertence - Hee applicab6e construcuan and operating exponence been considered 7 g Interfaces - Have the desagn mterface requrements been satsfled? g i Methods - Was an appropnate calculation method used? g QldlaW - le the output reasonable compared to inpute?

] ]

Accentance Crliaria - Are the acceptance creerte incorporated en the ca6culat on sufficient to allow venficebon tnet the desegn requrements have been setbefectority accomphehed? ] ] l Radiation Enneaura - Hee the calculation property coneadored radiation exposute to the pubic and plant personnoi?

]

Comments:

Sheet e 49 of 92 C-110t626-E540-020 NUCLEAR VERIFICATION PLAN /

SUMMARY

SHEET (EP-006)

Summary of vertfication scope, methods, results and conclusions.

Scope:

The scope of this review is to confirm that the use of the computer program. ARCON96 is controlled per GPUN Procedure EP-007.

Method:

Controlling the computer program involves an Installation Verification and Verification and Validation for the application j following EP-007.

l Results:

GPUN Memo written by Mr. T. Richter, E550 98-014 dated March 3,1998 (attached), documents completion of the Installation Verification and Verification and Validation of ARCON96.

Conclusions:

i ARCON96 is confirmed to be controlled per EP-007.

l Based on this evaluation, the calculation is venfied to be acceptable.

Venncation Engineer (print) Task 2: Richard J. McGoey (asn) f c**3qTT /

Use additional sheets if ned)e sary O

C.- 1Isl - tu - Gsys -ag e 3%*st s'o of W

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Mn n).orn n.du rn

\GUNUCLEAR l

subject: VALIDATION & VERIFICATION OF Date: March 3,1998 '

ARCON% PER 1000-ADM-1230.10, REV.O j From: T. A. Richter- Engineer, Projects Location: Morris Corp. Center E550-98-014 1

To: File l I

The United States Department of Energy's Energy Science and Technology Software Center has provided I GPUN with a copy ofit's ARCON96 program for mlal*g atmospheric relative concentrations in building wakes. This program has been installed and run by Ken Boughton:

Resident Equipment Number: 19687 Program name . ARCON96 l Version: 1.0 1 Executable file, size, date, time: ARCON96.EXE 380,928 bytes 12/15/97 12:17AM The program was delivered with a test case to vertfy correct installation. This test case was run on January 27,1998 (see attached test case output) and the resuhs match those provided in the program litemture. This l verifies ARCON96 correct ncrmlfarion.

i ARCON96 was employed in GPUN Calculation C 1101-826-E540 020 Rev 0 on March 3,1998. The ARCONM output was validated by the checkmg and design venfication of this calculation by Keith Woodard of PLG, Inc., on March 3,1998.

Under the provisions of 1000 ADM 1230.10, ARCON96 is approved for use in Level 3 applications (see attached 1000-ADM-1230.10 Rev 0 Exhibit 1 Checklist)

The ARCON96 program has been added to the Mechanical / Structural Engineering Controlled Software List.

T. A. Richter Extension 7427 TARkc Attachments Cc: K. G. Boughton - Engineer, Mechanical / Structural Engineering R. J. McGoey - Manager, Mechanical / Structural Engmeering TAR \MSWi3309solett

C.-Il o l -Pe%-Esvo- oh 3Me ss' s*1 aq F L.

COMPUTER SYSTEM SCOPE / CLASSIFICATION

_ CHECKUST (REF: 1000 ADM 1230.10 Rev 0, Exhibit 1)

COMPUTER SYSTEM or PROGRAM: ARCON961.0 t Questions Relating to Scope Yes No 1 Does the COMPUTER SYSTEM / PROGRAM perform a NUCLEAR X SAFETY RELATED function?

2 Does the COMPUTER SYSTEM / PROGRAM provide control functions for X plant hardware?

3 Does the COMPUTER SYSTEWPROGRAM provide data used to make X decisions regarding plant operation. design, or emergency response?

4 Does the COMPUTER SYSTEWPROGRAM perform radiation monrtonng? X 5 Does the COMPUTER SYSTEM / PROGRAM support training including the X Replica Simulators?

8 Does the COMPUTER SYSTEM / PROGRAM perform secunty functions? X 7 Does the COMPUTER SYSTEM / PROGRAM perform onvironmental X monrtonng?

8 Is the COMPUTER SYSTEM / PROGRAM under the scope of the GPUN X Operational Quality Assurance Plan?

If the response to ALL of the above questions is NO. then this procedure (1000 ADM-11230.10) does not apply to the computer system / program under consideration. If ANY of the responses are YES, then the computer system or program is covered by this procedure; proceed to the next set of questions.

Questions Relating to Classification Yes No 1 Does the COMPUTER GYSTEM/ PROGRAM perform a NUCLEAR X SAFETY RELATED function?

2 Does the COMPUTER SYSTEM / PROGRAM directly control plant X equipment and/or systems that are necessary to ensure the reliable generation (including outages and decommissioning) and/or transmission of power? Examples would be the digrtal feedwater or turbine control systems.

3 Does the COMPUTER SYSTEM / PROGRAM provide data for monrtonng of X power plant operating conditions to personnel making decisions controlling the operation of the plant? An example would be the Plant Computer

. System (PCS). ~

4 Is the COMPUTER SYSTEM / PROGRAM REGULATORY REOUIRED or X does it sat:afy other local requirements or commitments?

If the response to question 1 is "YES*, the classification is Level 1; formal V&V is required..

If the response to question 2 is "YES*, the classification is level 2, but consideration should be given to performing formal V&V on the computer system / program.

If the response to question 3 or 4 is "YES*, the classification is level 3; V&V is discretionary.

if the response to all of the questions in this section is "NO* the classification is level 3.

IN SCOPE: YES X NO CLASSIFICATION LEVEL: 3 VERIFICATION AND VAL! OAT!OH WtLt.SE PERFORMED: Y** v "A ~'

Mgr Signature

C.-Ils 1 - 8% -ENo - o2.e

%T* 5"2 oh f'l APC04 Fit.t EXasW o. set Portion Printed 1 27 98 t.S:ugnt:n

!XMT ST 1 9999999 99 9999999 EXMET ST 11 115 . 8 6 89 34 EXMET 87 12 62 6 5 91 62 EXMET ST 13 68 9 5 97 39 EXMET ST 14 '88 76 95 31 .

.EXMET ST 1 5 . 78 6 6 89 33 '

EXMT 87 16 109 8 5 72 .33 EXMET ST'1 7 65 7 5 87 34 EXMET ST 14 103 6 5 86 28 EXMT 57 19 106 7 5 89 28 EMMET 87 110 47 5 6 95 24

.EXMET ST 11's 64 8 4 82 19 EXMET ST 112 67 6 4 94 21 EXMET 87 113 51 10 6 M '29 EXMET ST 114 77 7 6 76 23 EXMET ST 115 M T 4 88 30 '

EXMET ST 116 M T4 81 35 EXMET ET IIT 63 14 6 88 55 EXMET ST 118 71 16 6 88 60 EXMET ST 119 TT e4 89 36 EXMET ST 120 85 5 5 80 62 EXMT ST 121 83 5 6 77 36 EXMET 87 121 TT 8 6 81 34 EXME1 87 123 350 4 4 108 17 EMMET ST 2 00 00 4 130 14 EXMET ST 21 00 00 4 65 8 EXMT ST 22 00 00 4 54 16 EXMET ST 23 00 00 5 358 7 EXMET ST 24 00 00 6 33T 12 EXMET ST 25 00 00 4 355 4 EMMT 87 26 00 00 6 280 9 EXMET ST 27 00 00 6 276 26 EXMT ST 28 274 3 4 2M 39 EXMET ST 2 9 262 9 4 2M 50 EXMET ST 210 267 16 4 272 53 EMMET ST 211 273 18 4 267 55 EXMET ST 212 262 31 4.265 75 EXMET 87 213 25 9 28 4 263 TT EXMET ST 216 251 28 4 259 68 EMMET 87 215 253.27 4 257 68 EXMET 87 216 259 26 4 2M 82 EXMET ST 217 269 28 6 267 71 EXMET ST 218 257 31 6 265 77 EXMET ST 219 270 25 6 274 68 EXMET ST 220 282 24 ' 4 288 M EXMET 87 221 2M 22 6 283 67 EXMET ST 222 271 22 4 276 69 EXMET ST 223 276 23 6 278 T4 EXMET 87 3 277 21 4 2M M EXMET 87 31 281 23 4 286 59 EXMET 87 32 285 19 6 285 63 EXMET 87 33 206 21 6 283 , 58 EXMET 87 36 276 25 4 206 62 EXMET ST 35 26T 29 4 276 72 l

'EXMET 87 36 264 27 4 273 TT EXMET 87 3 7'2 h 27 4 271 75 EXMET ST 38 276 21 6 275 62 EXMET ST 3 9 268 21 4 273 55 EXMET 87 310 268 22 6 274 59 EXMET 87 311 270 23 6 271 63 EXMET ST 312 263 30 6 277 65 EXMET ST.313 277 30 6 285 70 *

EXMET 87 316 302.25 6 295 63

EXMET ST 315 307. 23 6 290 62 '

EXMET 87 316 276 28 4 277 69

EXMET 87 317 251 20 4 275 56 EXMET 87 318 332 8 5 269 53 EXMET 87 319 95 6 5 269 60 EXMET ST. 320 169 8.6 276 39

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C.- Ilot - ? A 4 - Ervo -o a. Unitcd Stateo Dcportmont of Enorgy Energy Science and Technology Software Center P.O. Box 1020. Oak Ridge .TN . 37831 TEL (423)S78 2606 . FAX (423)s784434 October 06,1997 A. Irani General Public Unlities Nuclear i Upper Pond Rd. Parsippany , NJ 07054

Subject:

Proof of Purchase for Request No. 16717

Dear A. Irani:

This letter transmits the ARCON96 software package #00ll69IBMPC00, and should be used as your proof of purchase for the above software. Ycu should retain this letterforfuture reference regarding the purchase of upgrades or related softwarefrom the Energy Science and Technology Software Center (ESTSC) or other vendors. Enclosed, please find the packing list and the software with related documentation. If you have any questions, please contact the ESTSC. Sincerely, Aj D D,elores Brabsort I

D ~I\O\~ BA(o- 6sys one Energy Science and Technology Software Center M I 97 o f- 7 I ~ P. O. Box 1020 Cak Ridge, TN 37831 USA ' Telephone (423)576-2606 User I. D.: 9486 Fequest No.: 16717 For: A. Irani General Public Utilities Nuclear 1 Upper Pond Rd. Parsippany , NJ 07054 PACKAGE ID: 001169IBMPC00 ACRONYM ARCON96 MEDIA: 2 3.5 Diskettes DOCUMENTATION TO INCLUDE: Media Directory Software Abstract Installation Instructions NUREG/CR-6331 Rev 1 Media Includes Source Code, Executables, Sample Problem Input and output Data I 3

e C., - n lO % - %Me - O TV3 - 0 A o EST5 C Jt+E B T" PT oP ff pggg g ENERGY SCIENCE & TECHNCLOGY 3CFTWARE CENTER SOFTWARE ABSTPACT CATE 10/06/97 PACKAGE ID - 001169IBMPC00 KWIC TITLE - Atmospheric Relative Concentrations in Building Wakes AUTHORS - Ramsdell, J.V. Jr. Pacific Northwest National Lab., Richland WA (United States) Simonen, C.A. Pacific Northwest National Lab., Richland WA (United States) LIMITATION CODE - UNL AUDIENCE CODE - UNL CotOLETION COOR - 05/01/97 PUBLICATION DAzz - 05/01/97 DESCRIPTION - ARCON96 was developed to calculate relative concentrations in plumes from nuclear l power plants at control room air intakes in the vicinity of the release point. I PACRAGE CONTENTS - Media Directory Software Abstract Installation Instructions I NUREG/CR-6331 Rev 1 Media Includes Source Code, Executables, Sample Problem Input and Output Data 1 SOURCE CODE INCLUDED - Y l HEDIA QUANTITY - 2 3. 5 Dis kettes METHOD OF SOLUTION - ARCCN96 implements a straight-line Gaussian dispersion model with dispersion coefficients that are modified to account for low wind meander and building wake effects. Hourly, normalized concentrations (X/Q) are calculated from hourly meteorological data. The hourly values are averaged to form X/Qs for periods , ranging from 2 to 720 hours in duration. The calculated values for eacn period are used to form cumulative frequency distributions. CCMPUTER - IBM PC OPERATING SYSTEK -MSDOS 5.1 or higher programs will run in DOS window in Windows 3.1 and Windows 95 PROGRAbeCNG LANGUAGES - FORTRAN, VisualBasic SOFTWARE LIMITATIONS - ARCON96 is a single user program. If expanded output is selected by the user, the file includes the hourly input and X/Qs and the intermediate computational results. The output file may exceed a megabyte in size. l

C. -It o l- S2 fe = 2 TV0 - o,q e ESTSC St+eds- 29 e e 9 2._ FAGE 2 ENERGY SCIDICE & TECHNOLOGY sc r4ARg ce;7gg SOF"'*4ARE ASSTPACT ; ATE 10/36/97 PACKAGE ID - 001169IBMPC00 UNIQUE FEATURES - ARCCN96 calculates atmospheric dispersion of material released in the vicanty of buildings at nearby receptors using hourly meteorological data. Normalized concentrations (X/C) are calculated for periods ranging from L to 720 hours in duration. The results are presented in a cumulative frequency distribution for each averaging period. Normalized concentrations exceeded no more than Sa; of the time are calculated from these distributions. RELATED SOFTWMLE - ARCON96 is an update of ARCON95. The distribution package includes a user-interface, the computational code, and a support program that allows the computational code to address memory not normally available to dose programs. OTHER PROG /0PER STS INFO - Meteorological data are input using hourly data files. The format for the data files is described in the users guide. Input is limited to 10 data files. HARDWARE REQS - ARCON96 is designed for computers using a 80386 or higher processor, 640 kilobytes of memory with 470 kilobytes of free at run time, and a VGA color monitor. A math coprocessor is required. The user interface is designed to run in the 50-line mode. TIME REQUIREMENT 5 - ARCON96 calculates normalized concentrations using hourly meteorological data. Program progress is displayed during calculations. With 100+ MHz computers, 5 years of hourly data can be processed.in about 1 minute. REFERENCES - J.V. Ramsdell Jr. and C.A. Simonen, Atmospheric Relative Concentrations in Building Wakes, NUREG/CR-6331 Rev.1 (PNNL-10521 Rev.11, May 1997. ABSTRACT STATUS - Submitted 6/3/97. Released tested 6/24/97 SUBJECT CLASS CODE - R SPONSOR - NRC/NRR PACKAGE TTFE - TST EDE SUBJECT CATEGORIES - 990200 220900 220100 KEYWORDS - COMPUTER PROGPAM DOCUMENTATION A CODES BUILDINGS RADIOACTIVITY ' CONTROL ROCMS ) MATHEMATICAL MODELS MANUALS

C -//e / -pa 6 -Erys a. tastassaine/ READ.ME FEs fw ARCON96 f#sor 9., ,fs 4 I Version 1.0 of ARCON96 and its installaticn program, A96_ INST.B AT are included.on Disk 2. ARCON96 and the installation program are desenbed in detail in ATMOSPHERIC RELATIVE CONCENTRATIONS IN BUILDING WAKES, NUREG/CR-6331 Rev. I by Ramsdell and Simonen. INSTALLING ARCON96 ) The program may be installed by copying all files to your system, or it may be installed by changing to the directory containing the distribution disk and typing A96_ INST Drive Namel Name2 Name3 Named at the DOS prompt where Drive is the destination drive and Namel, Name2, etc., define the full path to the directory where ARCON96 is to be installed. Drive must include the drive letter specification and a colon. Namel, Name2, Name3, and Namn4 only require subdirectory names; they do not require any punctuation. Namel, Name2, Name , and Name4 may be omitted. The installation program will create the directory ific does not exist. It then copies the four files on the distribution disk to the specified directory. The two *.exe files on the distribution disk are self extracting archive files. ARCON96.exe contains the ARCON96 program files, and Examples.exe contains files related to the examples in the ARCON96 documentation. The contents of either of these files may be extracted by typing the name of the file on the command line in a DOS window. RUNNING ARCON96 ARCON96 is run by switching to the directory containing the program and typing ARCON96 f followed by pressing the ENTER key. This will bring up the user data entry forms. The j ARCON96 user's guide (NUREG/CR 6331 Rev.1) doscribes data entry and the information required by the program. 4 3 ARCON96 B ATCH FILE The ARCON96 batch file is set to run ARCON96 under either DOS or Windows 3.1. If you are running Windows 95, you will need to modify the batch file. The batch file contains instructions for the required modification. CODE DESCRIPTION t ARCON96 consists of six files. ARCON96. BAT is a batch file that sets the screen attributes and initiates code execution. ARCONVB is a Visual Basic for DOS program that is used for data input. ARCON96F is a FORTRAN program that performs the calculations, and ARCONVB2 is a Visual Basic for DOS program that returns control to ARCONVB. ARCHELP is an ASCII text file that contains help information used by ARCONVB. The last file is DOSXMSF.EXE. This file is needed to enable the ARCONMF to access extended memory. It must be accessible to ARCON96F either by being in the same subdirectory or by being in a subdirectory listed in the path statement. ARCON96 REOUIREMENTS

Personal computer with 80386 or Pentium processor and math coprocessor
3.5 inch disk drive '

i Hard Disk with 2+ Megabytes of free space

640 kilobses of memory (at least 470 kb free at run time)
VGA color monitor
mouse

C-11on- tu -E:va-o,7a, ARCON96. Page 2 of 2 ' Ment- 9/ or y t 11168 DeffatN 1777 85% 05-09-97 15:04 b541ad11 -w- EX5F_96.CFD

 '   4826 DeflatN 1719 65% 05-09-97 15:04 6fb54375 -w- EX5F_96. LOG 11188 DeflatN 1791 84% 05-09-97 15:04 cf335027 -w- EX6_96.CFD 4826 DedatN 1713 85% 0549-97 15:04 fee 8fdf4 -w- EXS_96. LOG 2911 DeflatN 1330 55% 05-05 9712:00 9359d95f-w- READ.ME 10402 DeflatN 3081 71 % 06-27 97 12:41 d0f6bb85 -w- XOQCALC5.WPD 10625 DeflaW 3693 66% 06 27 9712:41 dO9d97e8-w- ARCON96.WPD Disk 2 of 2 PKUNZIP EXE                                      29,378             02-01-93 2:04a PKUNZIP.EXE SOURCE ZIP                                       26,757             07-01-97 1:23p SOURCE. ZIP 2 file (s)        56,135 bytes O dir(s)        1,400,832 bytes free Unzipnad Filan Langth Method Size Ratio Date Time CRC-32 Attr Name 8781 DeflatN 2960 67% 06 27-9712:41 c7d5df0f-w- ARCON96.FOR 1932 DeflatN 748 62% 08-01-9612:00 9437fe65--+ CURVEFIX.FOR 4229 DeflatN 133169% 08-01-9612:00 caec5a8a-+ INIT.FOR 2951 DeflatN 949 68% 08419612:00 979eb095-w- INVMOL2.FOR 1515 DeflatN 569 63% 08 01-96 12:00 6d0efc35 -w- MET.lNC 4482 DeflatN 1350 70% 08 01-9612:00 a084f940-w- METREAD.FOR 3108 DeflatN 1025 68% 08-01-9612:00 a286 ebbs-+ NSIGMA1.FOR 604 DeflatN 290 52% 08-01-96 12:00 1678f423 -w- PARAM.INC 7625 DeflatN 2187 72% 05-09-9714:59 b9c8c889-+ PROC.FOR 4675 DeflatN 1336 72% 08-01-9612:00 Sa2364e5-w- RECORD.FOR 939 DefistN 384 60% 08 01-9612:00 bd5de1b7--w- SCENARIO.lNC 4925 DeflatN 1762 65% 08 01-9612:00 fd6ff041 -w- SCENREAD.FOR 1413 DeflatN 600 58% 08-01-9612:00 d4656edf-w- SHIFT.FOR
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SUMMARY

.FOR 1024 DeflatN 393 62% 08 01-96 12:00 803b2d53 -*- UNITS.lNC 2074 DeflatN 774 63% 08-01-9612:00 074e98c2-w WAKECORR.FOR 7157 DeflatN 2208 70% 08-01-96 12:00 if46 abo 2 -w- WINDYXOQ.FOR

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c -ii i -sar,- e re - . U. S. D:p3rtinest cf Enarry su,7 % ,g Energy Science and Technology S0fMare Center , Media Directory l ARCON96 #001169IBMPC00 Dhk I of 2 l ARCON96 ZIP 636,725 07-0197 1:22p ARCON96 ZIP PKUNZIP EXE 29,378 02 01-93 2:04a PKUNZIP.EXE . 2Sle(s) 666,103 bytes O dir(s) 791,040 bytes See Unzenad Filan Length Method Size Ratio Date Time CRC-32 Attr Name 14620 DeflatN 5250 65% 05 09 9715:00 3804baf2-+ ARCHELP.TXT 595 DeflatN 193 68% 05 09-9715:00 e29ddO0c-w- ARCON96. BAT 251274 De6stN 150543 41% 05 09 9715:00 9tul7eb46--w- ARCONVB.EXE 143612 DeflatN 94731 35% 05 09 97 15:00 b6846966 -+ ARCONVB2.EXE 380928 DeflatN 73161 81% OS27-97 12:41 16da602 -w- ARCON96F.EXE 393942 DedatN 176368 56% 01-11-94 00:00 2d837afa-+ DOSXMSF.EXE 398 DeflatN 149 63% 04 26-9614:161daa6bc8-w- EX1_96.RSF 398 DeRatN 158 61% 04-26 96 14:21 4d683c21 -w- EX2_96.RSF 398 DeGatN 155 62% 04-2S9614:24 c608ad99-w- EX3_96.RSP' 398 DeflatN 151 63% 04 26-9614:29 5e2411de-w EX4_96.RSF 387 DeGatN 155 60 % 05 02-97 08:50 fceddefb-w- EX5A_96.RSF 387 DeflatN 153 61% 0502-97 08:51 Sc6dWb8-w- EX58_96.RSF 387 DeflatN 152 61% 0502-97 08:52 4e7d9c42-w- EX5C_96.RSF 387 DeflatN 155 60% 0502-97 08:52 3ee9750f-w- EX5D_96.RSF 387 DeflatN 158 60% 0542 97 08:52 8b9d5ac3-w- EX5E_,96.RSF 387 DeflatN 159 59% 0542-97 08:52 d78877a9-w- EX5F_96.RSF 324120 DeflatN 83058 75% 0441-95 07:00 59626caf-w- EXAMPLE. MET 11168 DeflatN 1690 85% 0549-9715:03 d680 cia 4-w- EX1_96.CFD 4826 DefistN 1703 65% 0509-9715:03 8676a14c-w- EX1_96. LOG 11168 DeflatN 2558 78% 05-09 9715:03 cec 06233-w EX2_96.CFD

                 ' 4826 DeGatN 1747 64% 05099715:03 dc308e06-w- EX2_96. LOG 11168 De6stN> 1851 84% 05 09 97 15:03 fa6a6109 -w- EX3,96.CFD 4826 DeGatN 1715 65% 05 09-97 15:03 91432447 -> EX3_,96. LOG 11168 DeflatN 222T 81% 05-09-9715:03 d787efs2-w- EX4_96.CFD 4831 DeflatN 1769 64% 05-09 9715:03 80bes3fb-w- EX4_96. LOG                            l 11168 DeflatN 1800 84% 0549 97 15:03 e9c45cb3 -w- EX5A_96.CFD                         j 4826 DeflatN 1723 65% 05 09-9715:03 d3556s85 -w- EX5A_96. LOG                         j 11168 DeflatN 1738 85% 05 09-97 15:04 casc5076 --w- EX58_96.CFD                       '
         .   ,     4826 DeflatN 1725 65% 05 09-97 15:04 07fc87c4--w- EX58_.96. LOG 11168 DeflatN 1729 85% 05 09-97 15:04 89d764f9 -w- EX5C_96.CFD                        i 4826 DeflatN 1715 65% 0549 97 15:04 f99e943c -+ EX5C_96. LOG 11168 DeflatN 1814 84% 05 09-97 15:04 f16fc0bb -w- EX5D_96.CFD 4826 DeflatN 1726 65% 05-09-97 15:04 f4bc82f6 -w- EX50_96. LOG 11168 DeflatN 1721 85% 05-09-97 15:04 9eia34a8 -w- EX5E_96.CFD 4826 DeflatN 1718 65% 05-09-97 15:04 4f288339 -w- EX5E_96. LOG}}

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