ML20217E166

Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust

ML20217E166
Person / Time
Site:	Three Mile Island
Issue date:	03/18/1998
From:	Boughton K, Halitsky J 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-E540-022, C-1101-826-E540-22, NUDOCS 9803300399
Download: ML20217E166 (61)

Text

-

\G U NUCLEAR CALCULATION COVER SHEET Calculation Number: Rev. # System Number (s)

d. - 11o 1 - 816 - E 5 4 o - c 2 2. O 626 Sheet 1 of 6 l Calculation

Subject:

Gs r o mart of Y V /Q VA L VES FoR TMZ-t ccHTecu a vo s,, n o a 4 VG u IL A Tso u Gsenusr*

ls this calculation within the OQA Plan Scope?

(if Yes, a verification is required)

Does this calculation contain assumptions / design input that requires,isnfirmation?

O (if Yes, provide EDTTS No.(s)) $

is this calculation performed as a design basis calculation?

(if Yes, identify design basis parameters (section 3.3))

$0 CcNTROL AceM HAG o fA BILo TY Reference Source Documents (Calculations Safety Evaluations) (Section 4.3.1.3)

DOCUMENT NO. REV.NO.

I APPROVALS:

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Estimate of XwQ Values for TMI-l Control Buildmg Calc No Ro Nu Sheet So Vcntilanon S) stem Eshaust C-1iol x26-E540-022 0 2 of 61 1.0 PROBLEM STATEMENT:

In the esent of a generalloss of power to TMI l. and with hypothetical damper failures. the Dou ilirough the control room eshaust sent m the nonh wall of the fuel handling building will rescrsc. and air from the three-sided ucil betucen the reactor building and the fuct handhng buildmg util be drawn into the sent and ducted to Ihe control room.

If the loss of power should coincide with fracture of the containment structure and leakage of radioactisc gas to the atmosphere. some of the gas may be carned by the wind into the ucil and then mio the sent.

The purpose of this calculation is to proude an estimate of radioactiun concentration at the sent opening under the assumed concurrence of loss of power and gas leakage This concentration may then be used as a basis for discussion of a sy stem to ensure that possible coniannnation of the air reaching the control room will be within acceptable limits 2.0 SU%f M ARY OF RESUI,TS:

The results of the calculation are prosided as salues of Xu/Q(mi) at the sent for sisteen standard wind directions.

4 4 The salues are shown in Table i m Sec. 7 6 They range from 0 6 x 10 m to 2 6 X 104 mi To use these values in the X/Q calculation, a jomt frequency distnbution is a method used to determine the fracuon of time dunng a gncn penod that the wind occurs in each combmation of direction sector. speed class

- 2 and stabihty class. Then the value of X/Q(sec!m ) for each combination of classes is obtained by disiding the appropnate value of XwQ by the representaine umd speed u for that class. and multiplying by the fracuon of time for that combination The total X/Q is the summation of such salues. Note that values of Xu/Q in Table I are apphcable to all wind speed and stabihty classes Consenative assumptions hase been used in selection of dispersion models for the anal) sis. Uniform seepage through the entira surface of the reactor building abose ground was dn1ded into four release fractions i c. Mode I - through the reactor buildmg roof. Mode 2 - through the reactor wall into conuguous buildings. Mode 3 -

through the reactor wall into the atmosphere, and Mode 4 - mto the well between the reactor building and the fuel handhng building. In each mode the XwQ calculation was based on a combination of published wind runnel espenmental data on simpic building shapes and an estimate of wind flow pattems near the TMI l complex.

Consenatism was apphed in the following respects-

1) In all modes. the approach wind was assumed to be unaffected by large scale turbulence created by buildings such as the four coohng touets and the TMI 2 complet Such turtulence augments dispersion and reduces Xu/Q.

2) In Mode 1. all scepage through the roof was assumed to be entrained in the canty of the building complex.

In actuality. some of the scepage would pass downwind abose the caut , and then become entrained in the building wake. This ponion of the release would not return to the vent. Also. the itregulanties of the building contours uithin the caun would present the cauty return flow from reaclung the sent in some wind directions.

3) In Mode 2. some gas scepage would find its was to outl3 ng i building surfaces and escape mto the free atmosphere, thereby reducing the amount returmng to the sent.

4) In Mode 3. the walls of the reactor building were dnided into panels and the umformly - distnbuted seepage was assumed concentrated as a point source in the center of each panel. These pomt source releases esaggerate the intensity of the gas plume at the sent since some of the gas abose and below the point scurce W 'commomcalcil101 E540 022 doc

GPt3 NUCLEAN cal.CI'LATION %HEET Estimate of Xu/Q Values for TMI l Control Buildmg Calc No 16 w %cci . ,

Vcntilation S) stem Exhaust C-::al-x2r. E540 022 0 i of #.

would not reach the sent

5) Gas relcased jnto the ucll was assumed to be uniformly mned in the ucil. ignonng the probabic layenng of the gas adjacent to the reactor surfacc. ana) from the sent Also the well concentration vancs uwersci) as the s clocity of the local now entenng the ucil at its top and side opcmngs Low sclocines ucre assumed, thereby generaung high calculated concentranons it is not possible to make an accurate estunate o' the degree of consenausm in the calculanon es en by informed guesses regarding the abosc assumptions Houcs cr. n does not seem unreasonable to expect that the salues of Xu/Q in Table I are larger than the truc 5alues

3.0 REFERENCES

3.1 Ramsdell. Jr.. J V . C A Simonen t 1997)- Atmosphenc Relatne Concentranons m Building Wakes. U S Nuclear Regulaton Commission NUREG/CR 6DI. PNNL-luS21 Ret 1.

32 Hahtsky. J., J. Golden. P. Halpern and P Wu(1963) Wind Tunnel Tests of Gas Diffusion from a Leak m the Shell of a Nuclear Power Reactor and from a Nearby Stack. N.Y Unnersin Department of Meteorologs and Oceanography GSL Rep No 63 2 3.3 Halitsk). J. (1963): Gas Diffusion Near Buildings. N Y Unnersity Depanment of Meteorologs and Oceanography. GSL Rep. No. 631 34 Halitsky. J. (1968): Sec. 5-5 of Meteorology and Atomic Energy, D. H. Stade, ed U S A E C. Off of Infonnanon Seruces. NTIS TID-24190.

35 Halitsky. J (1998) Estimanon of X/Q m the Control Room Ethaust Air Duct Dunng an Accidental Breach of Containment unh Loss of Fan Power at Three Male Island Nuclear Plant. Umt 1. Report transmitted to A. Iraru of GPUN with letter dated Jan. 9.1998.

3.6 Hosker Jr., R. P. (1984): Chapter 7 of Atmosphenc Science and Power Producuon. D Randerson. ed . U S DOE-

, OSTI Pub No DOE / TIC-27601(DE84005177) 37 TMI l Construction Drawings provided by GPUN 12/22/97

4.0 ASSUMPTIONS

The equauons in Ref. I are not sahd for the current applicauon since local now condinons near the building surfaces ddier considerably from the umform Don Scla assumed m Gaussian models.

Wind tunnel model expenments using simple building shapes and surface releases are the best data source for estimating surface concentrations on comples structures The asatlable published data may be found in Refs 2. '

4. and 6. Some of the data in Refs 2 and 3 hate been reponed in Ref. 4. 5. and 6 houeser. the data that are mcst

. l relevant to the current con 0gurauon were not included Since Refs 2 and 3 are not readily asatlable. the omitted relesant Ogures are provided in App. A.

The test results in App A maybe comened directl> to full scale atmospheric concentrations at TMI I Wind speed proGle, buoyancv. stabihn and Reynolds Number mDuences need not be introduced sinec their etTects would fall within the bounds of accuracy of the prediction The data in App. A were obtained wah isolated buildings in the present case the reactor building is surrounded on three sides by other TMI-l buildings, the TMl 2 comples. and four coohng toucrs Therefore the approa:h Wfcommonicalcs!101 E540 022 doc

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GPEI Nt/ CLEAR CALCULATION SHEET .

Estimate of Xu/Q Values for TMI I Control Building Calc No Ro W Shce! No Ventilation S) stem Eshaust C-l101-X26 E540 022 0 4 of 61 How and the Gou around the TMl-l reactor building surfaces will depart significantl) from those ni the App A tests. especially in the wake of the adjacent TMI-I structure The effect of approach Cow disturbances will not be included The efTect of wind blockage by adjacent buildings is addressed by sketching umd flow p.itscrns represcnung the combmation of free and cavity Hows for the sixteen standard wind directions The diagrams are based on ihcorv and expenence. Thcs are presented m App 8. These patterns will be unafTected by the scepage and sent in0ou dynamics.

The assumed gas release configuration is umform scepage though the side and top surfaces of the reactor building.

5.0 DESIGN INPUT:

The control room sent innou rate is Suo cim. producing an maou s clocirt of o 05 nVs (sce Ref. 5t A simphfied scrsion of the building configuration prepared from the information in Ref.

• was prepared in Ref. 5. It is reproduced herein for convenience as Fig.1. The roof eles ations in Fig. I are for the tops of the parapets.

6.0 OVERALL APPROACH AND METHODOLOGY:

Leakage through the reactor building surface will diffuse m four modes:

1. Leakage through the roof will create an elevated plume that will pass os er the well and then descend into the building cavity where it will continue to diffuse in the cavity circulation.

2 Leakage through the portions of the reactor wall that are contiguous with adjacent buildings will circulate throughout these buildings and pass through the estenor surfaces into the building casity w here it will continue to diffuse in the casity circulation.

3 Leakage through the portions of the reactor wall that are exposed to the atmosphere will create plumes m the local flow. For cons enience in calculation. the exposed surface is disided into eight vertical panels w hose widths are the same as the widths of the contiguous buildings and whose heights are the scrucal distances between the contiguous building roofs and the top of the reactor building. Leakage through each panel will be treated as a point source at the center of the panel.

4 Leakage through the portion of the reactor surface that fonns the north wall of the well is mixed in the air now that passes along the reactor surface in the well and then across the s ent operung.

The distnbution of leakage as defined above defines elesen sources; one each in .sfodes 1. 2 and 4 and eight in Mode 3. Each source strength Q,(ci/s)is a fraction f, =A/A of the total release rate Q(ci/s). u here A,(m > s the mode surface area. A(m )is the total surface area and A=IA,.

The total concentration X(ci/m') at the sent is the sum of elesen mode concentrations. X(ct/m') calculated by use of concentration coefficients from published umd tunnel data. The anal > sis provides the quantities X u,Q t m1 4

and Xu/Q (m ). Values of X/Q and X/Q for a given hour maybe found by dividing by the as erage wind speed u(m/s) during that hour. Tower anemometer wind speeds without height corrections are sufficiently accurate for this purpose.

1.0 CALCL'LATIONS

Calculation work sheets maybe found in App. C.

The calculations are divided into sis sections:

C1 Release Fractions C2 Mode i Dispersion (Reactor Roof Source)

C3 Mode 2 Dispersion (Contiguous Building Source)

C-4 . Mode 3 Dispersion (Side Panel Sources)

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. Estimate of Xu/Q Valocs for_TMI l Control Hmldmg Calc No l<es W Sheci %

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C-6 Total Xu/O Subscripts I. 2.1. and 4 designate Modes 1. 2.1. and 4. respectach 7.1 Release Fractions The retcase fraction. f,. for cach source as calculated in Section C l. is as follou s Mode 1 reactor roof 0 189 Mode 2 - contiguous bmldings o 30M Mode 3 reactor panci 1 0 079 Mode 3 - reactor panct 2 0 091 Mode .1 reactor panct 1 o 066 Mode 1 reactor panct 4 o 057 Mode 3 - reactor panci 5 0 055 Mode 3 reactor panel 6 o oli Mode 3 reactor panel 7 0044 Mode 3 - reactor panel 8 0078 Mode 3 - total reactor pancis 0 503 Total surface 1000 7 2. Mode i Dispersion (Reactor Roof Source)

The roof effluent is assumed to descend downwind of the reactor and to diffuse m the cauty created by the BU-I building comples The closest wind tunnel test configuration is Fig A 1 showing a cubical building and a centered stack on the roof The aserage normalized concentration K at the building roofis about 2. Since K is dimensionless. it may be apphed on any scale.

Consersion of K to X iu,Q is gnen by:

Xi u/Q = Kf i/Au u here Xi si Mode I contnbution to the total X at any pomt. fi is the release fracuon and As is the largest side arca of the building A rectangular block approximation to the Dil-l butiding comptes (escluding the reactor building)is 325 fl wide s 325 ft long s 118 fi high >iciding A. = 3.562m . The relecse fraction fi = 0189 (frcm Sec. 7.1), Accordingly Xi u/Q = 2 s 0189/3562 = 01I s 10m' applicable at all locations near the building roofs in all wind directions.

7). Mode 2 Dispersion (Contiguous Building Source)

Scepage into contiguous buildings is assumed to escape to the cauty where it will behase as m Mode i dispersion. In ilus mode. f: = 0 308 and the Mode 2 contnbution is X:u/Q = 2 s 0 308/3562 = 017 s 10"m" 7 4. Mode 3 Dispersion (Side Panel Sources)

W ' common \cales1101 E540-022 doc

GPU NUCLEAR CALCL'LATION SHEET B.tunate of Xu/Q Values for TMl l Control Buildmg Calc. No M% Siiu;t No Ventilanon Sysicm Eshaust C l foi x26 E540 422 0 6 of 61 The st/cs and locations of the side pancis. the locations of their equnalent point sources and the locations of the centers of the side and top opcmngs mio the ucIl arc shown in Fig. 2.

All side panel leakage esentually enters the casily of the building compicx and produces Mode 3B dispersion analogous to Modes I and 2. Houcscr. some of the panel pomt sources lic directly upuind ofIhe ucil and contaminate the wcli before passing into the cauty. These sources follow Mode 3A dispersion Total contamination of the ucil by the panels is the sum of the tuo coninbutions 7.4.1. Mode 3 A Dispersion (Panel Sources Upumd of Well)

The appropnate wind tunnel model test for Mode 3A panels maybe chosen from Figs A 2. A 3 and A-4 These three tests emplo>cd mid-height releases which crudel) approsimate the heights of the panel point so.irces The procedures for detennimng L u/O at the ucll opening for a given panel release in a gnen wind direction is as follous:

a) Select the flow sketch in App. B for the specified umd direction.

b) Assign the panel source to the appropnate wind tunnel test source location. i e.. upu md. side or downwmd with respect to the wind direction c) Choose the well inflow openmg (side or top) b3 inspection of the Ocw sketch.

d) Determine the honzontal angle between the panel source and the well opemng.

c) Read K from the bottom figure at the honzental angle m d) and at elevation 2.iD = 0 6 f) Find f, for the panel source from Sec. ? 1.

g) Cornert K to Xu u/Q by the same formula as presiously used. but with As equal to the side projected area of the reactor buildmg. i c.150 x 140/3281; = 1.951mh Xu u/Q = Kf31951 / = 513 X 10" Kfi m4 7.4 2. Mode 3B Dispersion (Panel Sources other than Mode 3 A)

Mode 3B dispersion is analogous to Modes I and 2 but the source strength fraction is the sum of the fractions not included in Mode 3 A dispersion for the gnen wind direction The calculanon for X+ ucQ is gn en in Sec. C-4.-

7 4.3 Total Mode 3 Dispersion Calculation of Xu /Q u and Xie /Q uand their sum X3u/Q are shown in Sec. C-4 The sums are also shown in Table 1 in Sec. 7.6 7.5 Mode 4 Dispersion (Well Source)

Flow in the well is strongly dependent on wind direction. and may assume a vanety of patterns. i e , in through the side and out through the top and sice 5ersa, and partial innow and outflow through each opemng The s ent wtil be contammated by the local air stream that picks up scepage by direct contact with reactor surface in the well and subsequently passes along the sent.

The calculation requires an estimate of the cross section area and Gow selocity of this air streair.. and an estimate of the reactor surface area that it traverses. Section C 5 contains work sheets for the calculatior of L a Q at the sent in each wind direction. Low now selocities and small airstream cross sections were assun ed in order to W3 common \calcil101 E540 022 doc

GPEI NUCLEAM CAI.CULATION SHEET Esumate of Xu/Q Values for TMI l Control Building Cale. No Ret No '

Sheet No Vcntilation System Eshaus C-l 101.x26-E540m22 0 7 of 61 generate conscnaincl 3higli concentranons The s alues of Xi u/Q are shown in Table 1

~6 Total X u/Q The total X u/Q at the s ent is the suin of contnbutions in Modes 1. 2.1. and 4 Tbc Mode tatues and their sum

.are shown in Tabic I Table i Mode and Total Values of 10' X u/O(m2 )

Wind Mode i Mode 2 Mode 3 Mode 4 i Angle Roof Conuguous Bldg Pancis Well Total l 000 0 11 0 17 0 64 i I 54 2.46 022 5 0 11 0 17 0 74 1.27 2 39 04f 0 11 0 17 0 97 1 36 2.61 067 5 0 11 0 17 0 39 1 37 2.04 090 0 11 0 17 0 70 0 14 1 12 l ll2 5 0 11 0 17 0 28 0 0 56 135 0 11 0 17 0 71 0 0 99 157 5 0 11 0 17 0 66 0 68 l 162 i 180 0 11 0 17 0 28 0 1056 202 5 0 11 0 17 0 28 0 0 56 225 0 11 0 17 0 28 0 0 56 247 5 0 11 0 17 1028 0 0 56 +

270 0 11 0 17 l036 0 0 64 1 292 5 0 11 0 17 l 0 64 0 l 0 92 315 0 11 0 17 i 0 67 0 l 0 95 337 5 l 011  ! 0 17 l027 0 68 l 123 i l

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Vent:la::en 5ptem Exhaust C.: 10t 8:5 Ef40 022 0 l 3: . : l' i

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GPU NUCLEAR CALCULATION SHEET Est: mate of XuO Values for TMI I Control Building C.de No Ri s. 9::: s.-

Ventilation 5 3stem Exhaust C-1101326-C540 022 0 3 e : ~- t '

?. - ',s, T /~ 1_

3 a c

~ ~. 4 .

_ MORTH i

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1 Qou NUCLEA R CAI.CtILATION SHEET 4 Estimate of XwQ Values for TMI I Control Bmlding Calc No Rev No Shect No Ventilation S,sstem Eshaust C 1Itll x26-E5404122 0 12 of 61 APPENDIX C CALCLLATION WORKSHEETS W \commonicalc\l101 E5404)22 doc 4

Gipu NUCLEAN CALCULATION SHEET Estimate of Xin/Q Values for TMI l Control Buildmg Cale No Ro % Sheet No C-Il01-x26 E540422 a u re,i a

Vcntilation S.sstem Ekhaust C-1 RELEASE FRACTIONS i

Assume a simphfied reactor building shape consisting of a scrtical cslinder hasing height = 150 Ft. and diameter

= 140 ft.

Roof Area = n x 702 = 15,394 Ft.2 Side Area = x x 140 x 150 = 65,973 Ft.2 Total Area = 15394 + 65973 = 81,367 Ft.2

)

Rool Area Fraction = 15394 / 81367 = 0.189 Side Area Fraction = 65.973 / 81367 = 0.811 Penmeter = n x 140 = 440 Ft.

Side Panel Building 0, included S, Arc z , Building h, Panel Panel ,

f. Panel No. Beneath Angle Length Roof Height (Ft) Area (Ft.') Area Panel (Deg) (Ft) Height (Ft) Fraction 1 Heater 114 139 104 46 6394 079 Bay 2 Aux-Low 51 62 30 120 7440 091 3 Aux - Low 37 45 30 120 5400 066 4 Ground 25 31 0, 150 4650 057 5 Access 30 37 30 120 4440 055 6 Ground 15 18 0 150 2700 033 7 Inter - 26 32 37 113 3616 044 Low 6 Inter - 62 76 67 83 6308 078 High Total 360 440 40948 503 arc length = 140 x ( 0 / 360 ) panel area = s x h panel height = 150 - z panel area fraction = panel area / 81367

, l Wacommonicalc\l101 E540422 doc e .

Qeu NUCLEAN CALCULATION SHEET '

Estimate of Xu/Q Values for TMi l Control Building Calc. No. Rev No 5hect No Ventilation System Eshaust C Ilul-x26-Ef 4n 022 0 3 t ef 6:

Contiguous Building Surf aces:

(By Subtraction)

Area Area Fraction Total 81367 1.000 Roof 15394 0.189 Panels 40948 0.503 Buildings 25025 0.308 Secpage Area in Well = Arca of Nonh Wall of Fuci Handling Building:

height = 70 Ft.

width = 62 Ft.

Area = 70 x 62 = 4340 Ft.2 Area Fraction = 4340 / 81367 = 0.053 The wcll scepage area is located in the lower 70 Ft. of panel 2.

Wicommonicalcil101 E540422. doc 1.

GPU NUCLEAR CA1.Clll.ATION SHEET Esnmate of Xu/Q Valucs for TMi l Control Rmiding Calc No kes No Venulatiori 53 stem Eshaust Sheet No C I tol-X26 E540 022 H U of /,1 C2 MODE 1 DISPERSION Plume Desent into Cauty l

7 -

l 32 A

4 118 -

/

h 325 W Bmiding Cavity X' = K f Q / Ao u Ao = side area of building

= 118 x 325 = 38350 Ft. 2

= 3562 m 2 f = 0.189 (Section C 1)

K = 2 (average value over building surfaces in Fig A 1)

Background in Cavity Flow X'l Q = K f / Ao

=

2 x 0.189 / 3562

= 0.11 E-03 m 2 W'commonscalc 1101 E540-022 doc

Goa NUCLEAR CALCULATION SHEET Estimate of Xu/Q Values for TN11 1 Control Building Calc No l(o W Ventilation S 3stem Eshaust Sheet '.o C-I lo l-x26-F 40ul22 o  % are,i C3 MODE 2 DISPERSION Same a Mode i but f = 0.308 X' u / Q = 2 x 0.308 / 3562 = 0.17 E-03 m'2 C-4 MODE 3 OlSPERSION I

8 A N g 7 2 Side Release l

Release Point 0 Deg. From North p Deg. From Side a Deg. From Top of Well(W) (2) of Well 1 103 107 (+ 253) -083 (277) 2 186 -024 (+ 336) 000 (306) 3 231 4

+021 (-339) +045 (-315) 262 +052 ( 308) 5 +076 (-284) 290 +080 (-280) 6 + 104 (-256) I 327 +117 (-243) 7 + 141 (-219) 348 +138 ( 222) 8 +162 ( 198) {

016 194 (+166)

W 170 (190) l 210 l

i

( + = Clockwise)

( = Counterclockwise)

I Wncommon\ calc \1101-E540 022. doc ,

LG NUCLEAR U CALCULATION SHEET l Estimate of Nu/Q Values for TMI l Control Building Calc No Ro No Shcct 50 Ventilanon 5sstem Eshaust r-Ilol 826 E540-022 0 17 of 61 A = side projected Area

= 140 x 150 / 3 281 2

= 1951 m X" = K f Q / A u X"/ O = K f / A = K f / 1951 = 513E 04 K f m 2 Wind Well Source Total Direct. Entry No. 1 3 4 5 6 7 8 f .079 .066 057 .055 .033 .044 .078 Top a -83 45 76 104 141 162 -190 Entry Side p 107 21 52 80 117 138 166 Entry 000 Side Release Side Side Side Side Upwind K 6 42 3.7 3.5 3.4 10' 20 .12 .10 .06 .08 l0  ; O 55 lX'u/Q  ! I I 022.5 Side Release Side Side Side Side Side Side K 6 42 3 3.7 3.5 3.4 2.8 10 20 12 .10 .06 .08 .11 0.67 X'u/Q I l 045 Side Release Down Down i Side Side Side lj Upwind I K 10 5 I 10 3

34 3.9 3.7 3.4 ;38

! .11 .06 .08 .15 0 89 X"u!Q l l 15  ! }

i i

) i i 067 5 Side Release Upwind K 4 f

10' O.16 X'u/Q 0.16 i

090 Side Release Upwind Down K 4 10

'10 3 0.16 0 34

.\ 'u/O ' ' 0 50 i i 112.5 Top Release K

3 10

! !00 W common'cale.1101 E410 07? .h

+

Geo NUCLEAR CALCULATION SHEET Estimate of Xu/Q Values for TMI I Control Buildmg Calc No Ventilation S,sstem Eihaust Wes G Sheu No C-iint x26-E540-022 0 4x of 61 X'u/Q ' l '

l l f 135 I i Side Ret. e Side i Side Upwind Upwind K 6 43 6 3.8

10) .20 .13 .17 .06 i X'u/O 0 56 i

157.5 Side ' Release Side Side Side Upwind K 6 4.3 l 3.9 3.8 10' 20 .13 .11 06 X'u/Q 0 50 l

l Wind i . Well Source Direct. . Entry Total No. 1 3 4 5 6 7 8 f 079 066 .057 .055 .033 .044 .078 Top a -83 45 76 104 141 162 -190 Entry Side p 107 21 52 80 117 138 166 Entry 180 Release  !

K 10'  !

X *u/O '

O 00 202.5 Release l K

10' '

X'u/O '

0 00 225 Release i K

10' i

X"u/Q '

0 00 247.5 Side Release Upwind K 1 f f  ;

2 10 .03 l +

X*u/Q l 0 03 270 Side Release Upwind Upwind i

. K 1 4 ,

1

10) .03 .12  :

X*u/O - '! 0.15 292.5  !. Release Side I Upwind i Upwind 1 K 6 4 5 10 .20 .12

.14 '

X*u/O ,

O 46 W:\ common \ calc \l101 E540 022 doc

LGPU NUCLEAN CALCULATION SHEET -

Estimate of Xu/Q Values for TMI-l Control Building Cale No Ites Ne s:,cci *.o C-l 101 -x26-E540422 0 W cf6I Ventilation S.sstem Eshaust l

315 Release Side Side Upwind Upwind .

! i K 6 4.3 4 3.9 '

3 10 20. .13 .11 .07 X*u/O l l O S1 337.5 Release ,

, K i 10'  ! 0.00 X"u/O l l

I i

i i

W 'commonwalc\l101-E540422 doc

^

i

LGPU NUCLEAR CALCt'I.ATION SHEET

. Estunaic of Xu/O Values for TNil l Control Building Calc No Re* No Sher No C 1101826-E540 022 0 40 or61 Ventilation System Eshaust MODE 3B DISPERSION (Panel Sources other than Mode 3A)

Assume entry into building wake cavity and diffusion as in Mode 1 2

K = 2. A = 3562 m , f = I f38 , 10 X38 u / Q = 2 I f a3 /3562 = 0.56 I f38 Wind Panel Source If38 10' '10'  ! 10' Dir. X38u/Q i l X3u/O X3 u/Q Values of fs l 1 2* 3 4 5 6 7 8

( l  !

000 079 057 .136 .08 .56 .64 022.5 079 053 .132 .07 67 .74 045 .079 .072 .151 .08 i.89 .97 067.5 083 066 057 055 .033 .044 .078 .416 .23

• 16 39 090 .090 .057 055 .033 .044 .078 .357 .20 ' ! 50 70 112.5 .079 .091 .066 .057 .055 .033 .044 .078 .503 .28 l0 , 28 135 079 j.072 .044 .078 .273 .15 56 j .71 157.5 079 091 .044 078 .292 .16 .50 66 180 .079 .091 066 .057 .055 .033 044 .078 .503 .28 '0 l .28 202.5 .079 .091 066 057 055 033 .044 078 .503 .28 0 ' 28 225 .079 091 066 057 055 .033 .044 .078 .503 28 i 0 l.28 247.5 079 .091 .057 .055 033 044 .078 .437 .25 ' 03  ! 28 270 .079 091 .055 033 .044 .078 .380 .21 l 15 .36 292.5 .079 .091 .033 044 078 .325 :18 ' 46 64 315 .079 .091 .044- .078 .292 .16 51  ! 67 337.5 .079 072 .066 .057 .055 .033 044 .073 .479 27 0 j 27

• Values of f e3 for panel 2 are the total panel fraction minus the fraction assigned to Mode 4 contamination in Section C 5.

W.'commonicale'.Il01 E540422 doc

GPU NUCLEAR CALCULATION SHEET Estimate of Xu/Q Values for TMI l Control Building Calc No Res No Sheci Nn Ventilation Spleni Eshaust C 1lol-826-E340-022 0 41of61 C-5 MODE 4 OISPERSION 000

• Wind A 62

"*" /

Vent.

Ak Ed. Area /

jg p 70 31 74 N

1. 15 r

N

x I

Reactor Surface Area l 4 140 Dia +

1 f h ^  !

( j  !

150

)

V ,

W.\ common \ calc \l101 Ek j

Gina NUCLEAR CALCULATION SHEET Estimate of Xu/Q Values for TMI I Centrol Buildmg Calc No Ventilation Sutem Eshaus Ro % Sheet No C l toi 826-E540 022 18 42 of 61 Reactor Surface Area Side S, = 140 n x 150 = 65973 Ft 2 Top Sr = n 140 2 /4 = 15393 Ft 2 Tolal = 65973 + 15393 = 81366 Ft #

= 81367 / 3 281 2= 75S9 mi Seeoaae Area Seepage Area = 31 x 50 = 1550 Ft 2 S' = 20 x 62 = 1240 Ft2 Tolal = 1550 + 1240 = 2790 Ft 2

= 259 m 2 Inflow Area

(

A' = 20 x 15 = 300 Ft2 l

= 27.9 m'

{

inflow Velocity o' = 0 8 u Added Gas

(

\

O' = (S'/ S) Q = (259 / 7559) Q = .0343 Q Added Concentration i

X' = O' / A' u' = (.0343 / 27.9 x 0 8u) Q X* u / O = 00154 = 1.54 E 03 m .2 Ws commen'cale-Il0 t.run.n?2 dx

_m

(2pu l NUCLEAN CALCULATION SHEET Estimate of Xu/Q Values for TMI I Control Building Calc. No Res No sheet .No Ventilation System Exhaust C l101 M26 E540422 0 41 of 61 022.5

• Wind I

/

A' Vent /

ML j, Ech

,4

=

I gxN 1 l

14 r

~

)

t 1

W icommons ealc\l101 E540 022 doc I

Qeu NUCLEAR CALCULATION SHEET '

Estimaic of Xu/Q Values for TMI l Control Building Calc. No __

Venulation System Exhaust Res No Sh:ct ';c, C l101.x26-E540-022 0 44 of r,i Seepage Area S' = 62 x 50 = 3100 /10.76 = 288 m 2 Inflow Area A' = 15 x 50 = 750 /10.76 = 69.7 m Inflow Velocity u' = 0,4 u Added Gas Q' = (288 / 7559) Q = .0381 Q Added Concentration X' = (.0381/ 69.7 x 0.4 u) Q = .00137 Q / u X'u / O = 1.37 E-03 m -2 W 'commonicalc\ll01 E540 022 doc

GPU NUCLEAR CALCULATION sitEET Estimate of XwQ Values for TMI I Control Building C.ile No R o .'. " Sheu No Ventilation S.ssicm Eshaust C IIfil M26 E540-022 0 45 of 61 045' Wind ,

62 o

/  : d I i

s. 25 / -

70 74 t

li P

N A

S' = 62 x 25 = 1550 /10.76 = 144 m 2 A' = 15 x 25 = 375 /10.76 = 35 m 2 u' = 0.4 u Q' = (144 / 7559) Q = 0 0191 Q X' = (0.0191 Q) / 35 x 0.4 u

= 0.00136 Q / u X' u / Q = 1,36 E 03 m .2 W tcommonscalc\ll01-E540 022 doc

\

U NUCLEAR CALCIILATION SHEET Estimate of Xu/Q Values for TMl l Control Buildine Calc No Rev No Slicct No Ventilation S,ssicm Eshaust C Il01-826-E540422 0 4(, of 61 l

f 067.5* Wind l

l 10 5 62

,< S'

< / tv 10 3 70 02 74 N

l / / ,, N "

N N 1

/

l 2

S' = 62 x 10 = 620 /10.76 = 58 m A' = 15 x 10 = 150 /10.76 = 14 m 2 u' = 0.4 u -

Q' = (58/7559) Q = 0.00767 Q X' = (0.00767 Q ) / (14 x 0.4 u) = 0 00137 O / u 2

X' u ! Q = 1.37 E-03 m W 'commonicalc\1101 E540 022. doc

1 GPU MUCLEAN \

CALCULATION SHEET  !

Estimate of Xu/Q Values for TMI I Control Building Calc No Res Ne Venulation 5) stem E.shaust Shee: No f C-Ilot M26 E54(N)22 "

C cf 61 I 090* Wind Y

i G.is Plume W nt l

g Esh.

Cann Air y /

j / Smooth Flow Toward Fac n

Cauty Air i

4 l

)

X' u / O = 0 Assume 10% of 067.5* Wind X' u / Q = 0.14 E 03 m ~2 W temmon catei101 Fun.n22 dx

VGPU WUCLEAN CALC 1'LATION SHEET Estimate of Xu/Q Values for TMI I Control Building Calc No Res Na shca No Ventilation System Eihaust C l101826-E5J0-022 0 4x oI61 112.5* Wind 1

i TB Wall j

~..-.

^'

Gas Plume I

)

/

l

.X' u / Q = 0 W\commorreale\1101.E540 022 doc

Geo NUCLEAN CALCULATION SHEET '

Estimaic of Xu/Q Values for TMI I Control Butidmg Calc. No Rev No sitect .' o Ventilation Sy stem Eshaust C-1101-826-E540422 0 49cfe1 135' Wind X' u / Q = 0 157.5" Wind Assume one half intermittency of 022.5' Wind X' u / O = 0 68 E 03 m .2 j

180' Wind X' u / O = 0 102.5' Wind l l

1 l

X' u /O = 0 l 1

225" Wind l

)

X' u /Q = 0 l

247.5' Wind X' u / O = 0 W3 common'calcil101 E540422. doc

LGPU NUCLEAR CALCULATION SHEET

- Estimate of Xii/Q Values for TMI l Control Huilding Calc No Re$ % Sheet No Ventilation System Eshaust C Ilal-x26-E540422 0 50 of 61 270' Wind X' u / O = 0 292.5' Wind X' u / O = 0 315' Wind X'u/Q =0 337.5* Wind 50 'A of 022.5* Wind X' u / Q = 0.68 E-03 m .2 W \commonscaleil101 E5404122 doc

Shoct 5' of 6 8

&G NUCLEAR C. I' o I - e : 6 - e 14 o - c : a Verification Plan / Summary Sheet (EP-006)

I w ot Verhceenan it i e . s w AN> sc nei e i et E n'3 1 M T c A L t G u h f

• C =4 ftem No. Method / Depth of Verification Required Req'd Compi. Dete

,[ VJRef f TWE M E T rf oI) ; A 5 5 c' e P T e c u s Aub A 6 s v 4.7 3 3/2/96 Assigned Verification Enyneer DR R. N /vlt/ R 0 sJ 7 Queirflod per 4.4.1.3.b O Ya* S ***'ad Justification for We6ver ya m c, n , , , , in ,. (,, , y g em , , , , aa9 ;, , y g u, , ug g a ,m a,, o ,, s ,, ; , i.g ,

Section Manager (SM)(syv vues ,, ., , , g,g,

, , l' r f ./ + 1._ 1 '

j; Summary of vennection ec, ope, methode, reeufte end conclusione.

4 Sct A r r Ac ns b SvMMARY

- n ... .i geged gyg thb oveW the 'M V 10 be eCCoptSDOe.

venacao.n En,===r tenras 3 . . L omev .

(*'onn D*" M9'/79 l

u.. .ooisio;.i.n t. is n.c....rv

, U ~s.7, ie,,7i

C. -//*/-gag-Esya -on MET 4~/a. J 4, j

........................................................ b @ .Q I R D ,d.Q @ ,,

\GUNUCLEAR e vm subject: DESIGN VERIFICATION WAIVER Date: March)R1998 FOR ROBERT N. MERONEY j From: R. J. McGoey - Manager, t.ocation: Morris Corp. Center i Mechanical / Structural Engineering E540-98-013 I To: File l

Reference:

Resume of Mr. Robert N. Meroney l

This letter is the waiver of Responsible Technical Review requirement for Mr. Robert N.

Meroney to design verify GPUN Calculation C 1101-826-E540-022, Rev. O, " Estimate of XU/Q Values for TMI-l Control Building Ventilation System Exhaust." The subject calculation determines the distribution of potential radioactivity from the reactor building into the Control Building Ventilation System through the exhaust dust. This calculation includes hand calculations and assessment of air flows in the vicinity of the duct.

As evidenced by the attached resums, Mr. Meroney is qualified to design verify this calculation. He has extensive experience in this area and has reviewed numerous 3 publications dealing with air and wind movement. His education and experience satisfies I the intent of the requirements of EP-006. With this basis, I waive the RTR requirement in .)

the assigmnent of Mr. Meroney as the Verification Engineer for this calculation.

fy2 ( K.G. auwna .)

Ge uT. m,4 7 R. J. McGoey i Extension 7950 RJM\cc Cc: K. G. Boughton - Engineer, Mechanical / Structural Engineering

[RMC

)

]

l l

l U.r .*.Ir %"' 407 CO 17I i

C - H o p- f M ~ Erya ~ e 2.1.--

SWMf" f/ f k 4 l June,19s7 Robott N. Moroney Biogrsonicai Cata

- MERONEY, Robert N., Professor, Fluid Mechanics and Wind Engineering (FMWE)

Program, Civil Engineering Department (1965-present); Director, Fluid Dynamics and Diffusion Laboratory (1985-present); FMWE Program Leader (1985-1987); FMWE-Coordinator (1991-present); Director, CSU/TTU Cooperative Wind Engineering Program (11"09 fat). Adjunct Professor at Texas Tech University, Lubbock (1989-present). Chairman, Engineering Science Major, (1978-1979), Colorado State University. Dr. Moroney holde a M.S$ (1963) and Ph.D. (1968) in Mechanical Engineering tirom the University of Califomia, Berkeley.

Dr. Moroney has had over thirty years of exponence in teaching and research on basic and applied problems of fluid mechanica. He has conducted research in atmosphenc transport, toxic and flammable gaa spille, fossil and nuclear powe( plant siting, wind power, urban air I pollution environments, drying in porous media, and wind engineenng.

Dr. Moroney le the author of more than 290 papero and reporte and has been principal and co-principalinvestigator of projecto exceeding 6.0 million dollars in value in the past twenty five yeans. He also has served as consultant to major engineenng firms and govemment agencies on atmosphenc dynamics and simulation. He has been invited to serve on a variety of workshop panels, chair and review professional meetings, present topical and review papers, and co-author a text on engineenng meteorology. In the spnng of 1997, Dr. Moroney was an invited' lecturer at a NATO '

Advanced Study Institute on Suoyant Conveccon in Geophysica/ Flows at Pforzneim.

Germany.

Dr. Moroney is currently CSU Director of the Colorado State / Texas Tech University Cooperadve Program in Wind Engineering (1989-1999). This multi-million dollar prcject sponsored by the National Science Foundation and supported by industry fccuses en problems associated with extreme wind effects on man-made structures. The prcject coordinates research by four CSU faculty, four TTU faculty, and some twenty undergraduate and graduate students.

Dr. Moroney was the recipient of a Clean Air Act Fellowship from the Environmental Protection Agency during 1972-73 at Imperial College of Science and Tecnnelegy.

London. During 1977 Dr. Moroney received a Fulbright Haye Grant to ce researen in i New Zealand, and he was appointed an Erskine Lecturer at the University of Canterbury, Christchurch. He was awarded the Alexarider von Humboldt Award from the West German govemment to spend a year at the Institut fur Hydroleg's und Wasserwirtschaft, University of Kartsruhe, West Germany dunng 1980-1981. anc :nis

-award was extended to spend six months at the Meteorolcgy institute. University cf Hamburg during 1994. Dunng this same pened he was a Guest Lecturer at the I

}

C ~ ]/o/ - t3 b - Ervo - et.1 SMitf 3~/ c d (a l I

.. June,1997 University of Hamburg, He received a DAAD German Language Scholarship for Sum. er 1980. He was awarded the 1984 Abell Research Award for Excellence in Professionailsm, Educadon, Research, and Service to students by the Colorado State )

University College of Engineenng. In 1987 Dr. Moroney was awarded a Mobil Oil l Foundadon Research Award to further his activities in hazardous gas release analysis.

In 1988 Dr. Moroney received the Dean's Council Award for Engineering Science for his service to the Engineering Science program as advisor and chairman. In 1990, Dr.

)

Meroney recorved the Dean's Council Award for Civil Engineering for his service to the department in laboratory development,. education and research. In past years four of Dr.

Moroney's students have won regional awards in student paper contests and the student chapter received an AIAA Sendix award in 1971. He and his wife, Joan, were appointed Danforth Associates in 1968 for recognition of good teaching and attempts to personalize the educational procesa, He is a reviewer for a variety of national professional joumals. He is a Registered Professional Engineerin Colorado, a Member of the American Society of Mechanical Engineers, an Associate Fellow in the American Institute of Aeronautics and Astronautics, a Member of the American Meteorological Society, the Air Pollution and Waste Management Association, the Amencan Association for the Advancement of Science, Amencan Association for Wind Engineenng, the Amencan Wind Energy Association, and Sigma XI. Membership in Honorary Societies include Tau Beta Pi, Phi Eta Sigma, Pi Tau Sigma, Chi Epsilon and Phi Kappa Phi.

9 4

gg CALCULATION VERIFICATION CHECKLIST shot 51 ce ci NUCLEAR ma gma, C- 6 sci - ? ;L i %, . ;. . ;

Calc. Title E > D M A T C 'I A UG VE E - F;*; ~ TMI L Calc. 00. ~^

~

' TRe'v .

.: 4 .* d :L ac,s ains, si n in A r o w ,as,i , g a u ,i v ., 7 C so vo -U2e - i Su o -Ci2l c Verification by: (Pont Name) _

Section fDate hR. R.N M e k c .uc1 W _ _ h :14 l jc Ptece a check merk in the opphceble bos (Yes. No, N/A) for each rtem.

• NO" may indicate the design or venfication is incomplete requiring a task request be assigned by the responsible Section Manager.

The Section Manager shalt review each *NO* response to determine af Task Request needs to be prepared.

"N/A* (Not Applicable) does not require any further action by the Verrfication Engineer.

The Verrfication Summary (VS) (Exhibat 7A) may be used to outline the Venrication Engineer's work or for comments deemed appropriate by the Venfestion Engineer.

ITEMS ' Review Check Desron Comohance Yes l No N/A Design input & Data Were the inputs correctly selected, referenced (latest revision) and incorporated into the cilculation?

,./

/

Assumptions . Are assumptions necessary to perform the calculation adequately described and reasonable?

Regulatory Requirements Are the applicable codes and standards and regulatory requirements, including issue and addenda, properly identified and are their requirements met?

/

V l

Crnstruction/ Operating Espenence Has appbcable construction and operating expenence been considered?

Y Int'rfaces Have the design interf ace requirements been satisfied?

I

/ (

V Methods Was an appropnate calculation method used?

Output - is the output reasonable compared to inputs?

4

/ l s

Ac*"ptance Criterie . Are the acceptance criteria incorporated in the calculation sufficient to allow verification ,

th t the design requirements have been satisfactorily accomplished?

/

{

Radiation Exposure Has the calculation properly considered radiation exposure to the public and plant p;rsonnel?

Comenents:

Ad %g , gf. /p g y c. Ac g N , OMd5 Cct. h u ( h la d'. Gv' V,P h&So {$3fa v e h L t< m A,a rs g y , A. o m , q/.

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C - h c r - 8 26 - c b 4 0 CJL Rie 0 FLUID MECliANICS and U g g'; e WIND ENGINEERING I;niuxsity I Dr. Robert N. Meroney, Professor b Engineerho Reneerch Corwer, Rrn# 8227 Voice- (970) 491 os74 FAX. '~ Departmet of CMt trer.6ering (970) 49166r1 ~ ~

I Emat rneroneygengr colostate edu ~M Fort Cc61ns. Coorado

• 805231372. U s.A.

March 4,1998 Mr. AdiIrani GPU Nuclear One Upper Pond Road Parsippany, New Jersey 07054 Your Ref: FAX: 4 February 1998

Subject:

Review of Estimation of Concentrations in the Control Room Exhaust Duct Calculations prepared by James Halitsky.

Dear Mr. Irani,

I have completed my review of the calculations provided by Dr. James Halitsky for the " Estimation ofX /O in the control room exhaust air duct during an accidental breach of containment with loss of fan power at Three Mile Island Nuclear Plant Unit 1.'

After review I believe the approach taken by Dr. Halitsky is reasonable and conservative. I considered each assumption posed, checked the geometries, sketches, and calculations prepared by Dr. Halitsky and found them appropriate. To check the details of Dr. Halitsky's approach I recalculated all numbers he proposed using a spreadsheet program. In every case possible I recalculated all numbers, and when input was based on opinion rather than measured values,I considered the nature of these choices. The K values chosen from the figures published in Halitsky et. al. (1963a,1963b,1968) may be considered reasonsbly conservative, since the presence of nearby buildings tends to increase characteristic areas and decrease K values. Although there were several places were values varied due to roundoff during Dr. Hahtsky's calculations these deviations are minor. The only error of substance I found was minor On page C 5A I believe two numbers were transposed. but the effect is small.

Since the selection of K=2 during Mode 1,2, and 3b was approximate, I did a small sens4tivity analysis to allow it to vary from 1 to 4. Given the summation of concentrations for some wind directions this may result in up to 100% variation in X u/Q valt es. This effect tends to be significant only when Mode 3a panel or Mode 4 well concentrations are small. If the variations are significant, you might like to do a simitar sensitivity analysis to the choices of K during the Mode 3 panel calculations.

I find that I have spent a total of 10 tours on review, consideration of altematives, and comparative calculations. Thus my consultant fee will be $2,500.00 if you have further question, please feel free to contact me by phone, FAX or e mail as noted in the letterhead.

Sincerely yours, s

Robert N. Meroney, Professor Fluid Mechanics and Wind Engineeri rogram.

Director, Fluid Dynamics and Diffusion Laboratory

Enclosure:

Signed and reviewed Calculation sheets and copies of new spread sheets.

Il'md Engineering ResCarch and Applicalwn Speuahsts

6 ~ Ii C I * $ 2.6 U ) H c - L -

Check of conculesene ty J Matsky of Xu/Q values for the M41 Contros Sw.iding Uentilsten 8 mesm 7 Exhause A6U C-Date Calculalano 18 Jet > 94 Checked ty Robert N Moroney 6 Ld G; lI p.g Date Checked 03.Mor.94 Calculations.

Cnect on Tat,4e 1 Mode and foral Values of x wo 10*3 (m*.2)

Halit st y Wind Made 1 Mode 2 Mode 3 Made 4 Total Totale  % Dev Totals  % Dev Totale  % Dev Derocleon Roof Conseg 83dg Panefs Wells Ke2 M s1 ge3 K e 1 to 2 K e 3 to 2 K me K s 4 to 2 000 0 106 0 173 0 643 1538 2.460 2.282 7.23 % 2.638 7.23 % 2.616 14 44 %

00225 0 106 0 173 0 752 1 367 2.394 2 221 7.37% 2.574 7.37% 2.761 14.74 %

045 0 106 0 173 0 971 1 367 2.617 2.436 4 98 % 2.79e 4 9e% 2.981 13 92%

0675 0 106 0 173 0 439 1 367 2 005 1.807 13.34 % 2.344 13.38 % 2.843 26.71 %

090 0 106 0 173 0 744 0 137 1.183 0.902 22.50 % 1A28 22.50 % 1.687 46.00%

1125 0 106 0173 0 282 0 000 0 541 0.281 40 00% 0.842 60.00 % 1.123 100.00%

135 0 106 0 173 0 725 0 000 1 004 0 783 22.08 % 1.226 22.04 % 1.447 44.12 %

1575 0 106 0 173 0 656 0 683 1 Sie 1.403 13.34 % 1.834 13.38 % 2.061 26.71 %

180 0 106 0 173 0 282 0 000 0 541 0.231 60.00 % 0 842 60.00 % 1.123 100.00 %

2025 0 106 0 173 0 282 0 000 0 641 0 201 -Go 00% 0.842 80.00 % 1.123 100,00%

225 0 106 0 173 0 282 0 000 0 541 0 281 60.00 % 0.842 50.00 % 1.123 100.00 %

2475 0 106 0173 0 279 0 000 0 568 0 298 -46 94 % 0.820 44.94 % 1.082 93.88 %

270 0 106 0173 0 363 0 000 0642 0 398 34.34 % 0 000 38.38 % 1.134 7689%

2925 0 106 0 173 0 642 0 000 0 921 0 890 2500% 1.182 28.00% 1.383 60.18 %

315 0 106 0 173 0 690 0 000 0 M9 0.738 23 83 % 1.200 23.83 % 1.431 47.65%

3375 0 106 0 173 0 272 0 643 1.234 0 969 22.31 % 1.509 22.31 % 1.786 44.82 %

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Subject:

DESIGN VERIFICATION WAIVER Date: March 20,1998 FOR ROBERT N. MERONEY From: R. J. McGoey - Manager, Location: Morris Corp. Center Mechanical / Structural Engineering E540-98-013 To: File

Reference:

Resume of Mr. Robert N. Meroney This letter is the waiver of Responsible Technical Review requirement for Mr. Robert N.

Meroney to design verify GPUN Calculation C-Il01-826-E540-022, Rev. O, " Estimate of XU/Q Values for TMI-l Control Building Ventilation System Exhaust." The subject calculation determines the distribution of potential radioactivity from the reactor building into the Control Building Ventilation System through the exhaust dust. This calculation includes hand calculations and assessment of air flows in the vicinity of the duct.

As evidenced by the attached resume, Mr. Meroney is qualified to design verify t_his calculation. He has extensive experience in this area and has reviewed numerous publications dealing with air and wind movement. His education and experience satisfies )

the intent of the requirements ot'EP-006. With this basis, I waive the RTR requirement in the assignment of Mr. Meroney as the Verification Engineer for this calculation. i

)

R. J. McGoey Extension 7950 RJM\cc  ;

Cc: K. G. Boughton - Engineer, Mechanical / Structural Engineering IRMC 1

1 l

RJM MSWJ4098013 i

_________.________j

a June,19s7 Robert N. Moroney Biographical Data MERONEY, Robert N., Professor, Fluid Mechanics and Wind Engineering (FMWE)

Program. Civil Engineering Department (1965-present); Director, Fluid Dynamics and Diffusion Laboratory (1985-present); FMWE Program Leader (1985-1987); FMWE-Coordinator (1991'present); Director, CSU/TTU Cooperative Wind Engineering Program (1989-present). Adjunct Professor at Texas Tech University, Lubbock (1989-present). Chairman, Engineering Science Major, (1978-1979), Colorado State University. Dr. Moroney holds a M.S. (1963) and Ph.D. (1966) in Mechanical Engineering from the University of Califomia, Berkeley.

Dr. Moroney has had over thirty years of exponence in teaching and research c,n basic and applied problems of fluid mechanics. He has conducted research in atmosphcJe transport, toxic and flammable gas spills, fossil and nuclear power plant siting, wind power, urban air pollution environments, drying in porous media, and wind engineenng.

Dr. Moroney is the author of more than 290 papers and reports and has been principal and co-principal investigator of projects exceeding 6.0 million dollars in value in the past twenty five years. He also has served as consultant to major engineenng firms and govemment agencies on atmospheric dynamics and simulation. He has been invited to serve on a vanety of workshop panels, chair and review professional meetings, present topical and review papers, and co-author a text on engineenng meteorology. In the spring of 1997, Dr. Meroney was an invited lecturer at a NATO -

Advanced Study institute on Buoyant Convection in Geophysical Flows at Pforzheim, Germany.

Dr. Moroney is currently CSU Director of the Colorado State / Texas Tech University Cooperative Program in Wind Engineering (1989-1999). This multi-million dollar project sponsored by the National Science Foundation and supported by industry focuses on problems associated with extreme wind' effects on man-made structures. The prcject coordinates research by four CSU faculty, four TTU faculty, and some twenty undergraduate and graduate students.

Dr. Meroney was the recipient cf a Clean Air Act Fellowship from the Environmental Protection Agency during 1972-73 at Imperial College of Science and Technoicgy,  ;

London. During 1977 Dr. Meroney received a Fulbright Hays Grant to do research in ]

New Zealand, and he was appointed an Erskine , Lecturer at the ' University of j

Cantertzury, Christchurch. He was awarded the Alexander von Humboldt Award from l the West German govemment to spend a year at the institut fur Hydrologie und )

' Wasserwirtschaft. University of Karlsruhe, West Germany during 1980-1981, and this )

. award was extended to spend six months at the Meteorology Institute, University of l Hamburg dunng 1994. During this same period he was a Guest Lecturer at the  ;

i J

June,1997 University of Hamburg. He received a OAAD German Language Scnolarsny fer Su.mmer 1980. He was awarded the 1984 Abell Research Award for Excellence in Professionalism, Education, Research, and Service to students by the Colorado State University College of Engineering. In 1987 Dr. Meroney was awarded a Mobil Oil Foundation Research Award to further his activities in hazardous gas release analysis.

In 1988 Dr. Moroney received the Dean's Council Award for Engineering Science for his service to the Engineering Science program as advisor and chairman. In 1990, Dr.

Moroney received the Dean's Council Award for Civil Engineering for his service to the department in laboratory development, education and research in past years four of Dr.

Moroney's students have won regional awards in student paper contests and the student chapter received an AIAA Sendix award in 1971. 'He and his wife, Joan, were appointed Danforth Associates in 1969 for recognition of good teaching and attempts to personalize the educational process.

He is a reviewer for a variety of national professional joumals. He is a Registered Professional Engineer in Colorado, a Member of the American Society of Mechanical Engineers, an Associate Fellow in the Amencan Institute of Aeronautics and Astronautics, a Member of the American Meteorological Society, the Air Pollution and Waste Management Association, the American Association for the Advancement of Science, Amencan Association for Wind Engineenng, the American Wind Energy Association, and Sigma XI. Membership in Honorary Societies include Tau Beta Pi, Phi Eta Sigma, Pi Tau Sigma, Chi Epsilon and Phi Kappa Phi.

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