ML20236F667

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Summary of 980527 Meeting W/Util Re Control Room Habitability Evaluation Related to Control Room Operator Thyroid Dose from Fission Product Releases During Postulated Design Basis Accident at Plant Unit 1
ML20236F667
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1998
From: Colburn T
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-MA0246, TAC-MA246, NUDOCS 9807020275
Download: ML20236F667 (72)


Text

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  • f Cth p k UNITED STATES g j t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001

%..... June 30, 1998 l

LICENSEE: GPU Nuclear, Inc.

)

FACILITY: Three Mile Island Nuclear Station, Unit No.1 (TMI-1)  !

SUBJECT:

SUMMARY

OF MAY 27,1998, MEETING WITH GPU NUCLEAR, INC. ,

REPRESENTATIVES AND NRC STAFF TO DISCUSS CONTROL ROOM I HABITABILITY (TAC NO. MA0246)

On May 27,1998, GPU Nuclear Inc. (GPU or the licensee) representatives met with members of  ;

the NRC staff to discuss the licensee's Control Room Habitability evaluation related to control  ;

room operator thyroid dose from fission product releases during a postulated design basis i accident at TMI-1. The meeting was requested by the licensee to facilitate review of the  !

licensee's March 24,1998, submittal" Control Room Habitability for Maximum Hypothetical  ;

Accident." The licensee analyzed the control room operator thyroid dose and performed a I reanalysis of the operator whole body / skin dose and concluded that the results were below the General Design Criteria (GDC) 19 dose acceptance criteria and Standard Review Plan (SRP) 4 section 6.4 guidelines. A list of attendees is provided in enclosure 1. A copy of the licensee's ,

slides is contained in enclosure 2. i l The licensee had previously been required to address only the whole body and beta skin doses in  !

its response to NUREG-0737 Item lli.D.3.4, " Control Room Habitability." Consideration of thyroid doses from iodine releases was to be deferred until a source term reevaluation effort by the staff ,

was completed. As the staff has yet to complete its implementation plan on the use of revised I accident source terms for operating plants, the licensee was requested by letter dated i September 24,1997, to provide the results of its evaluation of the thyroid doses within 6 months of that letter. The staff had previously met with the licensee on December 12,1997, for a

! progress meeting.

During the May 27,1998, meeting the licensee provided the staff with a discussion of the control /

building emergency envelope description, the atmospheric dispersion modeling, and the control l room dose analysis. The licensee indicated it does not have continuous monitoring of control room pressure, nor does it have Technical Specifications requiring positive pressure in the control room. However, the licensee committed to perform periodic surveillance to verify control room positive pressure and to test control building ventilation system flowrates during emergency f recirculation operations. These commitments were also reflected, in some lesser detail, in the licensee's March 24,1998, submittal. The licensee also provided the staff with the results of

' recent control building differentia! pressure and air flow testing data and a comparison of the 1998 and 1985 data for these tests.

The atmospheric dispersion discussion included a three dimensional model of site buildings in and arpend the control building ventilation exhaust and the control building air intake structure.

The licensee hired a noted meteorology expert, Dr. James Halitsky, as consultant to provide its presentation on this topic. The staff provided several questions to the licensee in this area which were discussed and to which the licensee made a formal response on June 19,1998. These questions are containnd in enclosure 3. The licensee also provided more detail on periodic testing and inspection of (1) the control room to verify design basis positive pressure; (2) isolation dampers; (3) the emergency evelope door seal; (4) control building air flow rates; and the ventilation duct inteakage test program as part of the June 19,1998, response.

9807020275 980630 I ~ 'h I h[

PDR ADOCK 05000289 P PDR  ;

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The licensee analyzed the thyroid dose and whole body dose to control room operators for three cases, a base case with the normal configuration for the emergency recirculation mode and no in leakage at the exhaust damper; case 1, where a damper failure prevents isolation of the first floor of the control building; and case 2, where a switch failure prevents shutting the exhaust damper with resultant back leakage. Case 2 was determined to be the limiting case but in all cases the doses were calculated to be within the limits of GDC 19 and the SRP section 6.4

_ guidelines. The licensee concluded that the requirements of GDC 19 and NUREG-0737, item lil.D.3.4 were met. The NRC staff will be performing independent calculations to verify the licensee's conclusions.

The licensee requested staff approval by June 30,1998, but the staff could not assure the lice 1see that it would complete its review by that date.

Original signed by Timothy G. Colbum, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - 1/11 1' Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosures:

1. List of Attendees
2. Slides
3. Request for Additional Information cc w/ enclosures: See next page )

i HARD COPY E-MAIL i Docket File SCollins/FMiraglia (SJC1/FJM) CHehl(CWH)  ;

PUBLIC BBoger (RPZ) BMCabe (BCM L

OGC JZwolinski(JAZ) DScrenci(DPS)

PI-3 Rdg. CThomas (COT) JRaval(JHR) l ACRS TColbum (TGC) l SLaVie (SFL)  !

TMartin (e-mail to SLM3)

JLyons (JEL) e JLee (JYL1) i CMiller (CLM1) l REmch (RLE)

LBrown (LAB 2) l TClark (TLC 1)

DOCUMENT NAME: G:\TM10527.mts To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with r.ttachment/ enclosure "N" = No copy OFFICE PDI-3/PM , l PDI-3/t.,A _g) /lC, PERB , , _ _ k.- PDI-)/D A/ l NAME TColbum F TClark l/U REmch /(ZK O'fhpNiE DATE 06/10 /98 06//0/98 06/2 9/98 OPMGT98 OFFICIAL RECORD COPY

_ _ _ _ _ - - _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ ______L

b I
  • 3 s 1

l Three Mile Island Nuclear Station, Unit No.1 cc:

Michael Ross Robert B. Borsum Director, O&M, TMI B&W Nuclear Technologies GPU Nuclear, Inc. Suite 525 l P.O. Box 480 1700 Rockville Pike l Middletown, PA 17057 Rockville, MD 20852 l

John C. Fomicola William Domsife, Acting Director

- Director, Planning and Bureau of Radiation Protection Regulatory Affairs Pennsylvania Department of GPU Nuclear, Inc. Environmental Resources

, 100 Interpace Parkway P.O. Box 2063 Parsippany, NJ 07054 Harrisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager,TMI Regulatory Affairs National Energy Committee GPU Nuclear, Inc. Sierra Club P.O. Box 480 433 Orlando Avenue Middletown, PA 17057 State College, PA 16803 Emest L. Blake, Jr., Esquire Mr. James W. Langenbach, Vice President Shaw, Pittman, Potts & Trowbridge and Director- TMI-1 2300 N Street, NW. GPU Nuclear, Inc.

Washington, DC 20037 P.O. Box 480 Middletown, PA 17057 Chairman Board of County Commissioners of Dauphin County

Dauphin County Courthouse Harrisburg, PA 17120 Chairman l Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L Schmidt Senior Resident inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

_ _ _ _ _ _ _ ____________ _ ___ ____ n

,l ",

A, ',

May 27,1998 MEETING WITH GPU NUCLEAR INC.

CONTROL ROOM HABITABILITY STUDY ATTENDEES Hamt Affiliation T. Colbum NRC/NRR/DRPE/PDl-3 C. Smith NRC/NRR/DRPE/PDI-3

- J. Lyons NRC/NRR/DSSA/SPLB J. Raval NRC/NRR/DSSA/SPLB L Lee NRC/NRR/DRPM/PERB R. Emch NRC/NRR/DRPM/PERB L Brown NRC/NRR/DRPM/PERB S. LaVie NRC/NRR/DRPM/PERB K. Boughton GPU Nuclear / Engineering B. Parfitt TMI/ Radiological Engineering T. Y. Byoun GPU Nuclear / Nuclear Fuels P. Bennett TMI/HVAC System Engineer A. Irani GPU Nuclear / Safety and Risk Analysis C. Hadman GPU Nuclear / System Engineering TMl D. Distel GPU Nuclear / Licensing G. Gurican GPU Nuclear /TMI Safety and Licensing l R. McGoey GPU Nuclear / Support Engineering Dr. J. Halitsky GPU Nuclear / Meteorological consultant.

l Enclosure 1

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  • GPU NUCLEAR INC.

CONTROL ROOM HABITABILITY STUDY May 27,1998 HANDOUT MATERIAL USED AT THE MEETING l

ENCLOSURE 2

t. ,

/

i TMI-1 CONTROL ROOM HABITABILITY EVALUATION MEETING MAY 27,1998 4

Enclosure 2

1 l

AGENDA INTRODUCTION (D. Distel)

CONTROL BUILDING EMERGENCY ENVELOPE DESCRIPTION (P. Bennett)

Control Building Design Control Building Ventilation System

. System Description

. AP and Aliflow Testing Performed

. Commitment to Test and Inspection

. System Maintenance and Repair ATMOSPHERIC DISPERSION MODELING Yard Intake X/Q (K. Boughton)

Ventilation Exhaust X/Q Overview (K. Boughton)

CONTROL ROOM DOSE ANALYSIS MHA Analysis Assumptions (B. Parfitt)

Cases Analyzed and Results (B. Parfitt)

Overview of Evaluation on the CR Habitability Design Basis Accidents (T. Byoun)

SUMMARY

AND CONCLUSION (D. Distel)

b, '

[.. . .

INTRODUCTION l e GPU Nuclear submittal dated March 24,1998 " Control Room Habitability for Maximum Hypothetical Accident"

  • Analysis of Control Room Operator Thyroid Dose e Reanalysis of Operator Whole Body / Skin Dose Radiological Consequences  !

Whole Body 0.3 Rem Skin 4.0 Rem Thyroid 29.0 Rem  !

  • Results are below GDC 19 limits and SRP 6.4 guidelines l

)

t CONTROL BUILDING VENTILATION ZONES

Definitions: Control Room (CR)- Elevation 355'

! of Control Building excluding stairwell and Control Building Hallway (Patio).

Control Building Envelope (CBE)-

Elevations 355' (CR), 338' and 322' of the Control Building, excluding stairwell and Control Building Hallway (Patio).

Control Building Hallway (Patio)- l Adjacent to west wall of Control l

Building Envelope, and elevation 380'  !

of the Control Building.

1 Controlled Access Area (CAA)-

Elevation 306' of the Control Building, l excluding the Hot Tool room area.

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1 ATMOSPHERIC DISPERSION MODELING YARD X/Q

. GEOMETRY CR VENTILATION INTAKE - UNDERGROUND TUNNEL ENTRANCE-91 M FROM CONTAINMENT

. ARCON96 MODELING GAUSSIAN - CORRECTIONS FOR WAKE & LOW WIND SPEED SUITABLE FOR TMI'S GEOMETRY & METEOROLOGY

. PRINCIPAL INPUT & ASSUMPTIONS INPUT 6 YEARS OF MET DATA USED ASSUMPTIONS DIFFUSE RELEASE (GROUND LEVEL)

DIFFUSE AREA EQUIVALENT TO CONTAINMENT CROSS-SECTIONAL AREA (BASIS FOR IY & IZ)

CODE DEFAULTS UTILIZED (SURFACE ROUGHNESS LENGTH, MINIMUM WIND SPEED, SECTOR AVERAGING CONSTANT)

CODE BENCHMARKED AGAINST CODE AUTHOR'S MODEL e

SUMMARY

0-2 HRS. 1.70E-04 SEC/M 8 2-8 HRS. 1.14E-04 SEC/M*

8-24 HRS. 4.60E-05 SEC/M 1-4 DAYS 3.65E-05 SEC/M 4-30 DAYS 3.03E-05 SEC/M 8 UPDATED TO INCLUDE MORE EXTENSIVE MET DATA APPLICABLE TO TMI-1 RETAIN CONSERVATISM l

l

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PARTIAL SITE PLAN FOR TMl-1  !

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LEAKAGE  !

ARCONM (GAUSSIAN MODEL) NOT SUITABLE DUE TO CLOSE PROXIMITY OF EXHAUST OPENING TO CONTAINMENT & NON-UNIFORM FLOW FIELDS e

DATA SOURCES FROM WIND TUNNEL EXPERIMENTS HAVE BEEN UTILIZED FOR DEVELOPING X U / Q VALUES (REF. DR. JAMES HALITSKY) i e

INDEPENDENT VERIFICATION DR. ROBERT N. MERONEY, PROFESSOR, COLORADO I STATE UNIVERSITY e

HOURLY METEOROLOGICAL DATA ( 6 YEARS ) WERE USED TO DETERMINE HOURLY X/Q VALUES e

EACH YEAR OF DATA WAS STATISTICALLY RANKED TO DETERMINE 95 ,90 ,80 ", AND 60 PERCENTILES OF X/Q CONSISTENT WITH MURPHY /

CAMPE CORRECTIONS FOR LONGER TIME INTERVALS l

  • ANNUAL PERCENTILE RANKINGS WERE THEN

! AVERAGED FOR USE IN DOSE ASSESSMENT MODEL

  • AVERAGED X/Q VALUES ALSO USED FOR 10 CFM INGRESS / EGRESS ASSUMPTIONS TO CR

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i Overview of Evaluation on the CR Habitability DBA l 1

e All the radiation-releasing accidents in Section 14 of FSAR are compared with MHA CRH dose.

Source term and the source-to-receptor configuration are main parameters for the comparison.

  • Source term comparison is done based on the first 24-hour release e UFSAR accident analysis assumptions and technical  :

specification limits utilized -

.

  • Building wake effect assumed Dose model and x/Q-value are based on the Murphy-Campe guidelines for comparative purpose l

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(Cu' ries) Distance (m)

MHA 8728 91 1.000 1.00E+00 MSLB 4741 112 0.915 4.97E41 OTSG Tube Rupture 1.94 112 0.915 2.03E44 FHA in FHB 2.76 83 1.046 3.31E44 )

FHA in RB 155 91 1.000 1.78E 02 Rod Ejection Accident 707 91 1.000 8.10E-02 WGDTR 11 38 1.807 2.28E-03 Loss of Elec. Power:

J

1. Loss of Load 0.0388 112 0.915 4.07E 06
2. Station Blackout 0.181 112 0.915 1.90E-05 SFCDA 4.33 83 1.046 5.19E-04 CONCLUSION:

MHA habitability dose bounds all other accidents and, therefore, MHA is the design basis Occident for the control room habitability design.

,. s . .

SUMMARY

AND CONCLUSION TMI-1 Control Room Habitability Analysis Results

- Satisfy intent of GDC-19 and NUREG 0737, Ill.D.3.4

- TlD-14844 conservative source term

. Periodic inspection of CBVS dampers and CBE door seals

= Periodic testing of CBVS flow rates and area pressures

. Breathing apparatus and potassium iodide available

. Request NRC approval by June 30,1998 l

4

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V 1

, EXHAUST VENTX u / Q PRESENTATION

( BY DR. JAMES HALITSKY)

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T - -

/ UilE F.1 a g 3 f ~4v'.G- ;;G.". - s f WTML W

{ , h luTiRM HIG H REAi."TO R

~ '

i hw n -

, ac. h.-t ,i mf -

a w

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.l L REF. EL. 500 FT WEST ELEVATICN TREE MILE 15!MiD WUClDR RA.kli UET i J. HAMT5KY 1/8/9B SCAL:1 ! !HO. 'OO FI l

  • 10 0 & -

8., 4

{. .

~

< A...

-s - :3.

,- 4. . . . ,

~

.. . gy ~ , _

~

l L o s t.t e s so;Tgggsy tcoki+JG NORTH 1

1 F

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l ., ,

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~

m *~;,.,. .

-. .e, .

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' col IM 6 EAST lOOtaW WofG)EAS T l

TR'l-\ Dullbir4G MODE L SCALE . I 181 = 20 FT

3 5

i' . ..

FLOW AROUND SHARP EDGED BUILDING Secondary Primary f low Woke Cavity flow streamlines boundary boundary streamlines 3 \'./t

/

_...i --.

7 __- +

s>'

.-m

~~&%,

S

- /p\

Mean wind j $ s, \  %

~ -

- f ".

N ;f , q 7f n -

direction g f f Y '

=.=' /

- /.

r PLAN VIEW l

c.

.- ~.

,c -

- ~.

[w r

sf \. C

\- \ ( / v, \ ,

N

_- 1 o  %

N% f N ,e 1

- t o%  ;

Looking Side Looking

! downwind view upwind i

IN NORMAL ORIENTATION REF - METEOROLOGY ANT) ATONDC ENERGY- 1968 .

I

r. .

6

[,,"' ,

FLOW AROUND SHARP EDGED BUILDING Secondary Primary f jo, ke Covity streamlines boundary boundary somlines \

M- i __a -r- s-M=

Moon wind direction A=G _s s

NC sN  ;/

s

\

i

/

/

-whyp,))'/ '~

d .

PL AN VIEW

, . , , ,. , ,, - s

.. .. s w _____- Q . Q

,' t ,' i j i \ N f \ / I Looking Side Looking downwind visw upwind IN DIAGONAL ORIENTATION O

REF. - METEOROLOGY AND ATOMIC ENERGY- 1968

1. .

E. - ,

FLOW AROUND A ROUNDED BUILDING p ,

/ Displacement none ,

^

y _

f

\

'g -

\ Stegnation poing M g

~~,~ ~,"#

( a ) PLAN VIEW upwind seooretion 'cevity

~ Displacement boundery po p ' ~~~~ ~ cavitybovnaGIy *~

foyer s / '- g zone

=%

/ ,  ;

_ _ _./ -- -

sockround' j g flow N N

woke I

k N l f A LB } )AC 1 x -ur A m  ;

. i /IN -

prUmory flowl worob vertice) k secondary flow

' ~~

( b ) SIDE ELEVATION I

a , i I \

\ \

1 l 7 A .) I I ( l l b4 (c)

VELOCITY PROFILE REF. - METEOROLOGY AND ATOMIC ENERGY - 1968 L-

. I. . .

. .( , .

g o.

WIND I 2 3 4 i

l 7g J isu m

) ' .,

I g --g P i -

5 6 7 8 P" .J "v RFilli mm m .--...

Fig. 6 _ Photographic Sequence Showing Diffusion of ~ Smoke Released at Various Points in the Longitudinal Centerplane through the Reactor Shell

1,

  • 9 WIND 9 10 ll 12 p-g +

~ .

s o. .y

+p -

bdtim&d m ~"

aBild mm d

!3 I4 15 16 . j a mu e __ __ll __ _

l

. 5 l

.. M .;

, ?A/?. AA% '/ lX

_mme naamm  ;

I 1

l Fig. 6 ( cont. ) Photographic Sequence Showing Diffusion of Smoke Rejected at Various Points in the Longitudinal Centerplane l through the Reactor Shell 4

F.

I 'o . ', 10 DERTVATION OF K IN MODEL TEST ACTUAL CONCENTRATION X K= =

REFERENCE CONCENTRATION (Q/Au) .

. K = K ( x, y, z)

Q / A u = CONSTANT VALUE FOR EACH TEST USE OF K IN PREDICTION OF FULL SCALE CONCENTRATION Xu/Q = K/A l

f .'

l

., l 11 l,, ',

I N g 8

,5 gg N ~

(N N /

x N ,- .

- t N "

% \ / p/

x \ N/ 7 ' y ' ,

[ x N/ p / 7 /

/

N / -

I3 N / P

\

/

FIG. 15 CONCENTRATION ISOPLETHS y, tt/10 5tock - Top-4 fps - 0 F w;nd  : 0 -4I5 P

, Kmax  : 114 6

l f.*

~ 12 .

i .' l

. . J

- se

. as d . y .a.a.' c.........s...i..

o I;

_ . - _ _ 7_ NN N T 8 N <

x s to # h A5 b \ '

/ \N \ \ >

  • , f a...... 3 x y 3 ,

sr *. < e ga j

_ ,, y ,

  • 4 lN / / !

V

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~8 /

[ 1

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i I _/,,**,*** \ \ N I I ' '

O '

0 1 2 ) x /D

............... i'

., N

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l'

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. . .m................

... ie il i

. . . .m x _

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> gp ,, ,

4 ,

- }, \, \, - , io m \ e \. N, \ii 6

)

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  1. , , _ ,s 4

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.\

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e .,,

, i. u . s . .

. _ . . t .. .. / \1 '

N' ' I  !

01

' i 'N ' '

l

~0

- d. ...
1 c4 0; 08 to il 64 is is to l, N' ll , ; NI '

o at c4 oc e6 lo it 14 f.C #8 to

- Y 'D ~ y /p n

^ A /

/4/w1 N e / \ L\ f

,o \ /m' / /\ / M / ,

/ // / \/ N.A r .4 / 3L \/ ', ,* ;,* ' * "' i k *g WAW

/ /// \/ \/ / / / \/

y v N \/ g,,,,,

V _5 /  % r 06 - i/ d

('

/

N'N NN #

,:
  • x e,

x . w xx ,i ,-

01 x x x e  ! D< N N o- av w ,w , e o.

e-l Fig. 9 K- ISOPLETIIS FOR GAS RELEASED THROUGli REACTOR SHELL Confi::uration: shcII alone Releate Pednt - mid height upulnd Wind : log profile,5.54 fps

13 i.

L& , i s...........c...,,.,,,,

i

. la -e-

% W N

8% # hNN~ N -

40

/ \NNNNN % i f

xxx x C6 f i N N N 'A t N.s .esi ... , x x g g g CG A N 4 i \ \

g w g g i N' / a i 04 , m e j j

'Of / f p j O

i # i /

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i #

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it y W 10 i

  • ./

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. # I 1" l 06 _# E i I

. f %r b b 04 q- f n  % ,_ g r

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1 01 i / \ N6 NI i r 3 .x x 0

i X i X

\ t \ i

  • 01 ~ f * \ V e ) i l

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l g_ , i

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IP \' \ I i /i ! M T 1 08

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if./In v - A l \ \ / \ t\

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l

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3

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. p g6 x.l 4/ /8 j i

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i ggiga /li 11 / I i i i\ 'i

  • 1 ei i f. Ii / !I i 6 'w m'/ i * * ! i ie i , i di 7

% .n n , ., i %om4 I

. . . ..  % ... ! . . . . . . . . . + .. . .. ...i .. .s Y/7 - WD

~

A -

A ....i....

~ E/ \

\/ Y\ / / \/ \/ . AAI M / \ //

> .. / \=...

LO g

/

\1 1 11 9 k \1 Ar

\/ \

i \ fi \1 \

r n moi .. / V/ TT # If I Ifl if T 09 w Y*] / A ,e i I v// V i / I (

Ob WJ/ is i W ^" JJ 00 \ \ / O

\ %L /

ot m, x . / ,

  • x - ,

. .- w in- i o- ur w w =*

Fig.14 K- ISOPLETHS FOR GAS RELEASED THROUGH REACTOR SHELL Configuration: shell alone Release Point : mid-height side Wind : iog profile,5.54 fps b_____.__________---------.------- - - - - --

__.-.-,...m.m...-

t,.

.
14 66 L..e i e.e s a. e c. ...,,i ... s.. ....

g4 -- _

'~

~ m ~%

gg V" ~% ^n ,N. N N

.N N *w N N 'N gg .X h

T 1.'% %"\ N T

N X

N m N

N

> 1 s,, i,..,,s. . pp_ \~

'T J J / \  %

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, j \, g \

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p j g

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/ N

/ N fI '

/

\,

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4

~

tO o,.. 4 s .. r. . . .

18 tG l H 7 y -

t.1 j-10 y as ,'

os

(# - .

_o 04 X_ _i l h- - ~'sN , N Nm i

\ N O2 l

';l::" M .. w \

3 N

3

's w

o '

t L ;h g/D a

L' 6 i t i i i I t ,. .. .. . s . . .i.. i r.........s...i..

14 N, g

! a l 3

.e x/o . ..as L4

-- ,m .. m/s . 3.s , i l

gg hM l\ l I N

'\i M\ t ') ' g -

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r J f > l O O o oJ. 04. o6 CS a) 61 44 a f, se lo o crL og c6 o& to g.L (4 gr. la IJ Y/D y/D s

i

=

gg A* 3 i

/A i

/ \ / \\ A\\ \\ / I A

\/ \/ \\ / l \ \ T A % '** \ D...s...d 1/Dy 1\f \ \\ \1 30 M se5\

\,l \f N,"o, , l c -i i x s e m os \ x x .. ... . -

l 1 w -....e l 04 x x g ~

os

\ 'q a 4r w nc e e'

, Fig.11 K- ISOPLETHS FOR GAS RELEASED THROUGH REACTOR SHELL Configuration: shell alone Release Point : mid. height downwied

. Wind : log profile,5.54 fps

1. .

! '. . '. ns DISPERSION MODES MODE 1. Through Containment Roofinto Atmosphere MODE 2. Through Side into Contiguous Buldlings MODE 3. Through Containment Side into Atmosphere MODE 4. Through Containment Side into Well

( No Dispersion Through Ground Surface)

CONTAINMENT SURFACE AREA FRACTIONS Reaion Area Fraction Dispersion Tvoe Roof 0.189 Mode 1 Contiguous Bldgs. . 0.308 Mode 2 Panels 0.503 Mode 3 TOTAL 1.000 l

./, ,

?. *

" ~ 16 MODE 1 DISPERSION

+

l P

/ ' "" "

Cavity A

32 a

[

118 ._

. . J/

W ~325 --->

Building Cavity X' = K f Q / An u A3. = side area of building -

= 118 x 325 = 38350 Ft 2 .

= 3562 m' f,= 0.189 (Section C-1)

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

Background in Cavity Flow Xi u/Q = Kf / A 3

= 2 x 0.189 / 3562

= 0.11 E-03 m

  • MODE 2 DISPERSION Same as Mode 1 but f = 0.308 X' u / Q = 2 x 0.308 / 3562 = 0.17 E-03 m-2

i

1. ,

3, .. .

17 MODE 3 DISPERSION l

1 N

0

% J .:s,___

2 4 W .

(WellEntry)

Side Release Release 0 Deg. From p Deg. From a Deg. From Point North Side of Well Top (2) of (W) Well 1 103 -107 (+ 253) -083 (277) 2 186 -024 (+ 336) 000 (306) 3 231 +021 (-339) +045 (-315) 4 262 +052 (-308) +076 (-284) 5 290 +080 (-280) +104 (-256) 6 327 +117 (-243) +141 (-219) 7 348 +138,(-222) +162 (-198) 8 016 -194 (+166) -170 (190)

W (Well 210 Entry)

(+ = Clockwise) ( = Counterclockwise)

I l

L____________-___-____-____

/. .

l y ..

PANEL SOURCES 18 E04 -

_ 40RTM l

l Q ]- s +as- f SERTCI '.04! Tut.BN!

1 f _

4tA'GF. DAY qa9 ,UMi ? .

- / i f E r.,) ,l

~

  1. *" " I $

I '-

  • 433 itsityn ucn
  1. ' - J m e--

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Ll - - - - . -

i ;3 i '

.. p I as . f *( e s FULL MAu.;,g; l

  • E NElls.btLCN Dj W m t.- ac,a '. #i

% \

. , ,- \ ,

l LUYtl OW 7

\

\

PL Ah! \/IEW LCC ATION . OF MAN NTt.KE i t

I ttREC.it 014 b b i E 4 .

AMU 4ED PAuft poi 4T 500R*.g YE T' fAuPL utuSER.

6 L 7 /G 5 4 3 2 / I ,

+ f '

r / 4 y r.7 ,- ,'-'

4'  ?.

t$0 r

% k (wsL

/

/,f^,,:/l'/ '_.

's,'.',,,',

l f/ ' . :/ ^.'$, / /,'d:W_ ' ,.

GR ALE 7 ,,e,,,,,,,, cou{sGUOUS BulLDl4G, ,

. LNROLLED REACTOR WAt.1.

IChlG i l IN

  • lCD E[

a uuttet 2As/*.e Hoo + .

t'

. 19

s. .

- 504 .-

_ uoRTH J
s l

T ' <

+ + ~ . - . J l

\ P

  • k u

5 W *LOM Tur.B14E l s 4 .

I'  !

j utAtee *gv . cpp  % ' uiy 7 .' ]

= r. )  ;

" R*"'c" ' ' ' ' * - - 6 433

' iurec .t 0 f \L_F i G l RGH I .,

r

/'

g ,

% TOR-x_

, a

- , e s .

li it , a. > . e i

  1. c 4 l- q f utt. mucuus
  • i :. x x LMERG.b't!.CCy NTW

/

O l'a { w tow / 1 -m ,

3 i

, ,N v - 9u

/

pq  %. .

Js x f

/ - _

s EGn. '

u v

\ '

N PLAK) VIEW

' , :.C l'OK :

M A N. ' C N E :r

\

-6.!

4 CAVITN FLOW PATTERN IN 045

  • WIND' o

O e

Wu-__._____.-.-___-___-_-=._-_. --_-..

1 L ..

e .

20 ,

MODE 4 DISPERSION l 045' Wind 1

l 1

4

~

62

^'

/ 72

/

(Exh.

D

~,

/

\

S' 25 [ _

i 70 74 15 l r

, ~

} .

S' = 62 x 25 = 1550 /10.76 = 144 m2 '

1 A' = 15 x 25 = 375 /10.76 = 35 m2 u' = 0.4 u i l

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

/ , ,

,. , 21 MODE & TOTAL VALUES OF 10 3 X u /Q VALUES ( m -2)

IN 16 WIND DIRECTIONS Wind Mode 1 Mode 2 Mode 3 Mode 4 Angle Roof Contiguous Panels Well Total Bldg 000 0.11 0.17 0.64_ 1.54 2.46 022.5 0.11 0.17 0.74 1.37 2.39 045 0.11 0.17 0.9'7 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 1.12 112.5 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 1.62 180 0.11 0.17 0.28 0 0.56 l

l

~

202.5 0.11 0.17 0.28 0 0.56 l 225 0.11 0.17 0.28 0 0.56 247.5 0.11 0.17 0.28 0 0.56 270 0.11 0.17 0.36 0 0.64 l 292.5- 0.11 0.17 0.64 0 0.92 l

315 0.11 0.17 0.67 0 0.95 337.5 0.11 .

0.17 0.27 0.68 1.23 9

l 4 ', .

Y , . ', *,

22 I

CONSERVATISM

1. OMIT ENHANCED DISPERSION CAUSED BY UPWIND STRUCTURES
2. ASSUME ALL ROOF SEEPAGE IS ENTRAINED IN CAVITY
3. ASSUME ALL CONTIGUOUS B ILDING SEEPAGE IS ENTRAINED IN CAVITY ,
4. ASSUME SIDE PANEL SEEPAGE EMANATES FROM A SINGLE POINT SOURCE
5. ASSUME WELL SEEPAGE IS COMPLETELY MIXED 4

l l

O

{ } h. ' 'f

,MI-1 MARCH 24, 1998 CONTROL ROOM HABITABILITY STUDY REQUEST FOR ADDITIONAL INFORitATION i

1. Provide a copy of the meteorological data used to calculate the X/Q values. Data should be provided in the format specified in Appendix A to Section 2.7, " Meteorology and Air Quality,"

of draft NUREG-1555, " Environmental Standard Review Plan." A copy of this format is attached.

2. Based on the input to the ARCON96 computer calculations, it appears that th'e meteorological data were measured at the 30.5 and 46 meter levels. Typically measurements are made at approximately 10 meters. Were the lower measurements made at 30.5 meters and, if so, why? Are the data used in the calculations based on the delta-T method of atmospheric stability categorization described in Regulatory Guide 1.23, "Onsite Meteorological Programs?" If so, between what levels are the temperature differences measured? If another methodology was used, what is the methodology and why is it appropriate for this assessment?
3. Were all data used in the analysis collected under Regulatory Guide 1.23 guidelines? If not, how were the data collected that did not meet the recommendation of Regulatory Guide 1.23 and why are the collection methodologies / conditions acceptable?
4. During the periods of data collection, was the tower area free from obstructions (e.g.,

structures, trees) to a distance of at least 10X the height of any potential obstructions?

Was the tower area retained as a " transpiring area" and reasonably free from micro scale influences to ensure that the data collected were representative of the overall site area?

5. A further description of the details related to the methodology, inputs, assumptions and the bases used to calculate the TMI ventilation system exhaust X/Qs would be helpful, including a discussion of the figures and tables provided in the March 24,1998 submittal.
6. Other than attempting to follow the example given in NUREG/CR-6331, Revision 1,

" Atmospheric Relative Concentrations in Building Wakes," were there other bases for the assumptions used to calculate the

  • yard intake" X/Qs?

Enclosure 3 ww Wyj~

( 'h i ',

1 l

  • APPENDIX A l
j. STANDARD FORMAT FOR HOURLY METEOROLOGICAL DATA l

l When hourly meteorological data are submitted to the NRC, the data may be submitted on mutually agreed upon magnetic media. The media may be disks or magnetic tapes. De data should be in files that are of a size that are convenient for use and storage. Annual data files are acceptable.

Use of a standard format for submission of hourly meteorological data will facilitate data evaluation and dispersion analysis. The standard data format is similar to the format described in Appendix A of )

Standard Review Pian 2.3.3 (NRC 1987). De only differences are in the first two fields of the data records. De second field has been increased to permit specification of the year using four digits rather than two, and the first field has been reduced from six bytes to four bytes and is now specified as a

! character string rather t' han an integer. De format for the remainder of the record is identical to the  !

format in SRP 2.3.3.

l l At the beginning of each file, use the first five (5) records to give a tape description. Include plane name,

! location (latitude, longitude), dates of data, information explaining data contained in the "other" fields if they are used, height of measurements, and any additional information pertinent to identification of the tape. Make sure all five records are included, even if some are blank. Format for the first five records will be 160A1. Meteorological data format is (A4,14,13,14,25F5.1, F5.2,3F5.1). Table 2.7 1 shows L the size and content of each field in the meteorological data records in the standard format. In addition, ,

it provides a form for recording supporting information about the meteorological instrumentation.

l All data should be given to the tenth of a unit, except solar radiation, which should be given to a hundredth of a unit. His does not necessarily indicate the accuracy of the data (e.g., wind direction is usually given to the nearest degree). All nines in any field indicate a lost record (99999). All sevens in a wind direction field indicate calm (77777). If there are only two levels of data, use the upper and lower levels. If there is only one level, use the upper level.

NUREG-1555 (DRAFT) 2.7-18 August 1997

,s c

( \.

Table 2.7-1. Hourly Meteorological Data LOCATION:

l DATE OF DATA RECORD:

l .A4. Identifier (can be anything)

.14. Year l .D Julian Day

.14. Hour (on 24-hour clock)

ACCURACY

! .fil. UpperMeasurements: Level = meters

.fil. Wind Direction (degrees) l .fil. Wind Speed (meter /sec)

.fLI. Sigma"Iheta(degrees)

.f1L AmbientTemperature('C)

. fit Moisture:

.f1L Other:

.f1L Intermediate Measurements: Level = meters

. fit Wind Direction (degrees)

.fil Wind Speed (meter /sec)

.fiL SigmaTheta(degrees)

.fil AmbientTemperature('C)

. fit Moisture:

.f1L Other:

J1L LowerMeasurements: Level = meters

. fit Wind Direction (degrees) l

.F1L Wind Speed (meter /sec)

.f1L SigmaTheta(degrees)

. fit AmbientTemperature(*C) i .f1L Moisture:

.fiL Other:

I August 1997 2.7-19 NUREG-1555 (DRAFT) i

)

['*s i

Table 2.7-1. (contd)

_E11 Temp. Diff. (Upper-Lower)(*C/100 meters)

.Eli Temp. Diff. (Upper-Intermediate)('C/100 meters)

.Eli Temp. Diff. (Intermediate-Lowerj ('C/100 meters)

.E11 Precipitation (mm) 2

.Eli SolarRadiation(cal /cm / min)

.E11 Visibility (km)

.E51 Other:

.E51 Other:

i 9

NUREG-1555 (DRAFT) 2.7 20 August 1997

- ___