ML20040D199

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Forwards Public Version of Basis for Exception to NUREG-0654 Criteria Re Prompt Notification Sys Design for Alerting Population within Plume Exposure Emergency Planning Zone.Substantiating Prompt Notification Calculations Encl
ML20040D199
Person / Time
Site: Midland
Issue date: 09/24/1981
From: Jackie Cook
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20040D198 List:
References
RTR-NUREG-0654, RTR-NUREG-654 13821, NUDOCS 8201300431
Download: ML20040D199 (17)


Text

. Ci James W Cook E b* ice Pressiens - Projects Engsnernng

.and Construcsson General offices: 1945 West Parnell Road, Jackson, MI 492o1 * (517) 788 o453 4

/ Oj s

' September 24, 1981 f g ,s 9\

Ys

' OCT 21931-Mr Harold Denton, Director t Office of Nuclear Reactor Regulation Division of Licensing h[ ,* 5 %'E$f US Nuclear Regulatory Commission .s

\{,,,'s]$;,Q' Washington, DC 20666 MIDLAND PROJECT DOCKET NOS 329 AND 330 PROMPT ALERTING AND NOTIFICATION OF THE POPULATION, EXCEPTION TO FILE B13.3 SERIAL 13821 ENCLOSURE: SUBSTANTIATING PROMPT NOTIFICATION CALCULATIONS NUREG 0654, Revision 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Appendix 3, Section B, provides the criteria for acceptance for the means of providing prompt alerting and notification of the population.

The minimum acceptable design objectives for coverage by such a system are stated as follows:

a. Capability for providing both an alert signal and an informational or instructional message to the population on an area-wide basis throughout the 10-mile EPZ within 15 minutes.
b. The initial notification system will assure direct coverage of essentially 100% of the population within 5 miles of the site,
c. Special arrangements will be made to assure 100% coverage within 45 minutes of the population who may not have-received the initial notification within the entire plume exposure EPZ.

Appendix 3, Section B, further states that the basis for any special requirement exceptions must be documented. This letter provides the documentation for such an exception based upon redoing, using Midland specific data, the calculations in which the NRC staff developed the generic critieria of NUREG-0654. It is, therefore, proposed that the Midland prompt g notification system within the plume exposure EPZ be designed to the following criteria:

a. Capability for providing both an alert signal and an informational or '

instructional message to essentially 100% of the population through direct ,j coverage on an area wide basis out to at least 5 miles from the reacter -

building within 15 minutes.

I I

8201300d51 011007 PDR ADOCK 05000329 PDR p

I

. m

b. Special arrangements will be made to assure 100% coverage.within.

45 minutes of the population who may not have received the initial notification within the 5-mile prompt notification area.

The method utilized for justifying a 5-mile warning area is provided in the enclosure. Basically, the same method was used by the Nuclear Regulatory Commission when it determined the definition of the primary EPZ, ie, the pathway in which an individual could receive a life-threatening dose of whole body external radiation in a postulated accident. In reviewing the assumptions made by NRC for parameters representing those of a " typical" plant (particularly core thermal generation and meteorological dispersion), it was found that the " typical" values were not representative for Midland.

Therefore, based upon the enclosure's findings, the Midland public prompt notification system will cover at least a 5-mile radius.

Statutes already exist requiring state agencies to protect the health and safety of the public. Should any protective actions become necessary outside the 5-mile prompt notification area, local and state agencies would coordinate these activities.

JWC/JNL/dsb CC PRBasolo, Director, Emergency Services, Mich State Police HBehmlander, Director, Emergency Services, Saginaw County RJCook, Resident Inspector, Midland RBDeWitt, P-26-117B JDuso, Admin Assistant to City Manager, Midland WKFreer, Director, Emergency Services, Midland County BKGrimes, NRC DSHood, NRC DBMiller, Midland PPPsomas, NRC DEVanFarowe, Mich Dept of Public Health DDWoods, Director, Emergency Services, Bay County i

oc0881-0512a102

1 SUBSTANTIATING PROMPT NCTIF~CATIO?T CAI,CULATIONS Whole body doses to the public as a result of a Class 9 accident vere caleu-lated based on actual Midland fifth percentile X/Q values (see at ached FSAR Table '2.3-26) and core inventories as presented in attached FSAR Table 11.1-2. The results of the calculations are presented in Table 1.

Note that all doses presented are 2h-hour integrated doses. The following is 'a description of the method and assumptions.

Method and Assu=;tions The whole body penetrating radiation dose rate due to i=cersion in a semi-infinite radioactive cloud =ay be written as (Reg Guide 1.h):

YD i = 0.25 5yi X.,

Where: -

YD~, = Ga==a dose rate from a semi-infinite cloud in rad /sec delivered by nuclide 1.

EYg = Average ga-" energy per disintegration of nuclide i (MEV/ dis) (see Table I attached).

X i

= Concentration of nuclide i in the cloud (Ci/m 3),

The concentrations and release rates for the noble gases =ay be written as:

Xi * (X/Q) Qi e- i , where Q g =Qd e i and Where: X/Q = Meteorological dispersion factor (sec/m ) obtained from two years of data collected on site. These plant-specific X/Q values are smaller than general X/Q values (at 1 m/s) listed in Reg Guide 1.h because the actual vind speeds are used to calculate them. The fifth percentile values which roughly correspond to stability Category F are used.

Qg = Release rate frcm containment for nuclide 1 (C1/sec).

A g

= Decay constant for nuclide 'i (sec-1) (see Table I).

T = Transit time from containment to 5 miles.

Qg' = Containment release rate for nuclide i at t = 0 (shutdown) eqcal to 100% of the total noble gas inventory for isotope i divided by 86,h00 see (2k hours), assuming uniforn release over a 2k-hour period. (See Table I.} ,

t = Time post-accident (sec), from 0 to 86,h00 see (2h hours).

Enclosure (1)

2 Thus, the dose rate equation becomes:

-A t i

-A m i'

yDi = 0.25 Eg (x/Q) qg e e The ' release is assumed to be uniform and to take place over a 2h-1 our period.

Following the suggeste:i method in Reg Guide 1.h. different X/Q va'.ues for 0-8 hours and 8-24 hours are used. Thus, the total integrated dote for nuclide i beco=es : .

2h hours 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2h, hours D dt =

Yi YD ,dt + i YD ,dt

' J s

0 0 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 28,800 see

- 86,h00 see

-AiT; -l T

= 0.25 EygQ,i y

e e

-Ag t

+' y e i2 ' -A t t

dt q e et 48 hr j 16 hr J

~

0 28,800 sec ,.

~

1 1 1 e

~i1 l-* 28,800 Ag

- l r = 0.25 Eyi Qoi A -

4 g 8 hr L l

_A T

-28,800 A, -86,h00 A,'

,1 i 2 , _,

e 2 16 hr A -

Where yT = 3,095 see is the 5-mile transit time for a 2.6 m/s vind speed which is the most probable vind speed found by ratioing the actual X/Q 8-hr values to the enes given in Reg Guide 1.h for a 1 m/s vind speed. (See Figure 1.)

T 2,1h5 see is the 5-mile transit time for a 3.75 m/s vind speed 2= vbich is found by ratioing the actual X/Q 16-hrvalues te the ones giren in Reg Guide 1.4 for a i m/s vind speed. (See Figure 1.)

8 hr= 1.3 E-5 sec/m3 (from Figure 1).

16 hr= -1.6 E-6 sec/m (from Figure 1).

Enclosure (1)

3 7

For the halogens, no transit time decay credit is allowed per Reg Ouide 1.h (T = 0). However, credit =ay be taken for halogen re= oval by containment sprays.

Of the 25% of the halogens in the core inventory which is i= mediately available for leakage from the centainment, 91% is in the elemental for=, 5% in the particulate for= and h5 in the organic form. Ncne of the organic halogens are re:noved by the sprays. Thus , assu=ing unifors release over 2h hours ,

the release rate for the organic iodines may be written as:

Qg = (0.04) Q01 e org Where: Q A. = Containment release rate for nuclide i at t = 0 (shutdown) equal to 25% of the total halogen inventory for isctope i divided by 86,h00 see (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />). (See Table I.)

0.0h = h% of the available 25%. (The fraction which is in organic for=.)

t = Time post-accident (sec), fres 0 to 86,k00 sec (2k hours).

Ag = Decay constant for nuclide 1 (sec-1). (See Table I. )

Elemental halogens are re=oved at a rate of - A,,N, where N is the halogen inventory at time t and vnere:

-l A

se

= 1.375 E-3 see . (See Table 15.6-10 of the Midland FSAR.}

Thus, the release rate for elemental halogens may be written as:

-A t -A,t

    • ^

Qg = (0.91) Q gy e e eles

-(A se +A)t i

= (0.91) Qci e Where : Qd = Containment equal to 25%release ratehalogen of the total for nuclide i at t = for inventory 0 (shutdown). isotope i divided by 86,h00 see (2h hours). (See Table I.)

0.91 = 91% of the available 25% (the fraction which is in the elemental form) .

t = Time post-accident (sec) (from 0 to 86,h00 sec (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)).

A g = Decay constant for nuclide 1 (see ). (See Table I. )

A' = 1.375 E-3 sec~1 (Spray removal constant for halogens in se the elemental fors. ) (See FSAR Table 15.6-10.)

Enclosure (1) r

h Using a similar argu=ent for nalogens in the particulate form, we may write:

- (1 *P + A,) t^

Qg = (0.05) Qg e part Where: Qg , t, and Ag are as defined above and where A = 9.25 E-5 sec-1 (Spray removal constant for halogens 3P in the particulate form.) (See FSAR Table 15.6-10.)

0.05 = 5% of the available 25%. (The fraction which is in the particulate form. )

The total halogen release rate Q, may nov be written as:

" total Qg = (0.0'.) Qd e i + (0.91) Q e - IA se * ^i}

tota,.

+

+ (0.05)-Qd e ~ ( sP 1

-A t 1

-(A 8' +A)ti

=Qd ', (0.Ch)e + (0.91)e

-(A + A,) t SP- -

+ (0.05) e The dose rate due to nGelide i is then written as:

-1 t i

-(A se +1)t i Dg = 0.25 E (X/Q) Qd (0.0h)e + (0.91)e I sp + Ai lt

+ (0.05)e .

3 3 Where X/Q g g = 13 E-5 sec/m for t ,s 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and x/q 16 hr = 1.6 M sec/m for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4 t.4 2h hours. Fur +hermore, DF for halogens must be limited to 100 per SRP 6.5.2/NUREG 75/087 a:Ad WASH-1329 Therefore, the dose rate contribution from the elemental and particulate halogens must not be less than 0.01 x dose rate at t = 0. For the elemental halogens, the dose rar,e contribution drops to 1% after 3,3h9 see'(from 0.01 =

-A set , , - ( 1. 37 5 E-3) t giving t = 3,3h9 sec). For the particulate halogens, e

the dose rate contribution drops to 1% after h9,785 see (from 0.01 =

-A t '

sp , , -(9.25 E-5)t giving t = 49,785 sec).

e Enclosure (1)

5 Thus, the total 2h-hour integrated dose for halogen isotope i becomes:

2k hours 3,3h9 see 22,800 see L9,785 see 36,h00 see e

l Dg dt = D dt + D dt + dt + D dt J -

fD -

0 0 3,3h9 see 28,800 see L9,765 see 3,3h9 see

-lA +

Ai i,t 3

= 0.25 E Q l 0.91e i se Oi Y

i Q

8 hr I J O see 28,800 see 28,800 see

-A t - (A 8P

+ 1i ):

+

)0.91(0.01)e dt + ,,0.05 e dt 3,3k9 see C 86'400 sea 28,800 see f

~

-At e

~At ) p '

I i +1 0.91 (0.01)e

+j 0.0L e at QM hr 0 # (28,800see h9,785 sec 86,h00 see

-(A sp + Ai )t -At

+

0.05 e dt + , 0.05 (0.01) e dt 28,800 see h9,785 sec 86,h00 see -

-At i

+ ,

0.0h e dt ,

28,800 see Integrating, we obtain:

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

[

f D1 dt = 0.25 E Qd j 0.91 1 , ,-3,3k9 (A,, + A1 )'

J \ 8 hr (A

. se

+A)i i i

0 -28,800 A }

0.0091 l -3,3h9 A g

+ -e )

0.05

-28,800 ts

+(A sp +A)i ,

1-* i) ,

Enclosure (1)

6 28,800 A .y O.0091 T -28,800 A -86,400 A g 7 t

  • 0.0h 1-* i 916 ~'

A g .

1. hr -

A i ,

l 0.05 I' ' (A sp *A)1

~h9'I03 ( A sp # A) i

,(A +A)g h9,785A -36,h00 A I + 0.0L f -28,800 A,* -86,' 400 A )

t i

+ 0.0005 i i , e _e e -e 4, , f.

3 I

  • 1 i Dese centribution due to each nuclide was calculated and listed in Table !.

Doses below 1 cres are not snown.

The total integrated whole body dose due to all nuclides is then found by su==ing the contributions frem each nuclide:

Sk hours Total dose = Dg dt i

g Using the above =ethod, the total integrated 2h-hour whole body dose delivered to sn individue.1 located at the center line of the clume five miles downwind from the Plant is found to be less than 65 rems (given 5 eereentile Midland Plsnt stecific x/Qs ) .

Enclosure (1)

TABLE I-

~

Midland Plant - Core Inventory at' t=0, Nuclide Data.

and Doses Initial Release Core Activ Dose (Rem)

Isotope A(See-1) -E(MeV)(1) (ciatt=0){gy Rate (ci/secQ,)(3) at 5 Miles Kr-83m' 1.03E-4 2.58E-3 9.25E+6 1.07E+2 6.05E-3 Kr-85m 4.38E-5 1.57E-1 2.19E+7 2.53E+2 1.93E+0 Kr-85 2.03E-9 2.21E-3 5.30E+5 6.13E+0 1.58E-3 Kr-87. 1. 52E-4 7.16E-1 4.00E+7 4.63E+2 4.38E+0 Kr-88 '6.90E-5 '1.81E+0 5.60E+7 6.48E+2 3.93E+1 Xe-131m 6.72E-7 3.27E-3 4.38E+5 5.07E+0' 1.90E-3 Xe-133m 3.55E-6 2.40E-2 3.07E+6 3.55E+1 9.09E-2 Xe-133 '1.52E-6 3.02E-2 1.27E+8 1.47E+3 4.98E+0 Xe-135m 7.37E-4 4.28E-1 3.26E+7 3.78E+2 7.30E-2 Xe-135 2.10E-5 2.45E-1 2.09E+7 2.42E+2 4.32Et0 Xe-137 3.02E-3 1.37E-1 - -

Xe-138 8.13E-4 9.87E-1 1.17E+8 1.35E+3 4.31E-1 Rb-88 6.30E-5 5.85E-1 ') 6.48E+2 1.27E+1 Cs-138 3.58E-4 2.24E+0 5.60E+7((5) 5.85E+7 6.77E+2 4.55E+0 Subtotal = 72.8 rem I-131 -9.82E-7 3.75E-1 1.84E+7 2.13E+2 7.40E-1.

I-132 8.52E-5 2.22E+0 :2.16E+7 2.50E+2 2.53E+0 I-133 9.48E-6 5.77E 3.20E+7 3.70E+2 1.76E+0 I-134 2.22E-4 2.46E+0 4.00E+7 4.63E+2 3.43E+0 I-135 3.05E-5 1.42E+0 3.18E+7- 2.68E+2 3.48E+0 Br-84 3.63E-4 1.63E+0 3.93E+6 4.55E+1 1.81E-1 Subtotal = 12.1 rem TOTAL = 85 rgg (1) From MEDLIST.

'() From FSAR Table 11.1-2 -- 100% noble gases; 25% halogens.

(3) Core inventory divided by 86400 see-(24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

(} In equilibrium with Kr-88 after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, starting with pure parent.

() Reaches max activity in 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> from' pure parent of Xe-138 (max activity approx 0.5 initial parent activity). .

miO981-0687a100 Enclosure (1)

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MIDLAND 162-FSAR TABLE 11.1-2

'IvrAL CORE FISSION PRODUCT ACT1VITY VERSUS TIME IN EQUILIBRIUM CYCLE Activity, C1, Ef fective Full Power Days Isotope 4 30 60 90 120 150 180 210 240 280 310 Br-84 1.57E+7 1.57E*7 1.57E+7 1.57E+7 1.57E*7 1.57E*7 1.57E+7 1.57E*7 1.57E+7 1. 57 E* 7 1.57E*7 Br-85 2.19E*7 2.19E+7 2.19E+7 2.19E*7 2.19 Ee 7 2.19E+7 2.19E*7 2.19E*7 2.19E+7 2.19E+7 2.19E*7 Kr-83m 9.25E+6 9.25E*6 9.25E*6 9.25E+6 9.25E*6 9.25E*6 9. 2 SE+ 6 9.25E+6 9.2%E+6 9.25E*6 9.25E*6 Er-85m 2.19E*7 2.19E*7 2.19E+7 2.19E+7 2.19E+7 2.19E+7 2.19E+7 2.19E*7 2.19 E* 7 2.19E*7 2.19E+7 Kr-85 2.84E+5 3.06E+5 3.31E+5 3.55E+5 3.7 9 E+ 5 4.04E+5 4.28E+5 4.52E*5 4.75E*5 5.01E*5 5.30E+5 Kr-87 4.00E+7 4.00E+7 4.00E+7 4.00E+7 4.0 0 E*7 4.00E+7 4.00E*7 4.00E+7 4.00E*7 4.00E*7 4.00E*7 Kr-88 5.60E+7 5.60E+7 5.60E+7 5.60E+7 5. 6 0 E+ 7 5.60E+7 5.60E+7 5. 6 0 E+ 7 5. 60 E+ 7 5.60E+7 5.60E*7 Rb-88 5.64E*7 5.64E+7 5.64E+7 5.64E+7 5.6 4 E+7 5.64E*7 5.64E+7 5.64Ee7 5.64E+7 5.64E*7 5.64E*7 Sr-89 4.64E+7 5.49E+7 6.15E+7 6.59E*7 6. 8 9 E+ 7 7.08E+7 7.21E*7 7.29E+7 7.35Ee7 7.40E+7 7.42E*7 Sr-90 2.12E*6 2.28E+6 2.46E+6 2.65E*6 2.83E*6 3.02E*6 3.20E+6 3. 3 8 E* 6 3.56E*6 3. 81 E* 6 3.99E*6 Sr-91 9.70E+7 9.72E+7 9.72E*7 9.72E+7 9.7 2 E*7 9.72E*7 9.72E*7 9.72E*7 9.72E*7 9.72E*7 9.72E+7 Sr-92 9.50E*7 9.50E+7 9.50E+7 9.50E*7 9.5 0 E* 7 9.50E+7 9.50E*7 9.50E*7 9.50E*7 9.50E+7 9.50E+7 Y-90 2.10E+6 2.26E*6 2.44E*6 2.62E+6 2.81E*6 2.99E*6 3.17E+6 3.36E*6 3.54 E* 6 3. 78 E* 6 3.96E*6 Y-91 6.23E+7 7.21E+7 8.02E+7 8.60E+7 9. 00 Ee 7 9.28E+7 9.48E*7 9.62E*7 9.72E*7 9.81Ee7 9.85E*7 Mo-99 8.16 E+ 7 1.28E*8 1.28E*8 1.28E*8 1. 28 Ee 8 1.28E+8 1.28E*8 1.28Ee8 1.28E*8 1.28E+8 1.28Ee8 Ru-106 1.0SE+7 1.21E+7 1.36E*7 1.50E+7 1. 6 3 E+ 7 1.75E*7 1.86E*7 1.97E*7 2.08E*7 2.20E*7 2.29E+7 Xe-135m 2.00E*5 3.26E*5 4.14E+5 4.34E+5 4.37 E+ 5 4.38E*5 4.3BE*5 4.38E*5 4.30E*5 4.38E+5 4.38E+5 Xe-133m 1.68E+6 3.06E*6 3.07E+6 3.07E+6 3.07E*6 3.07E+6 3.07E*6 3.07E*6 3.07E*6 3.07E+6 3.07E*6 5e-133 4.78E*7 1.25E+8 1.27E*8 1.27E*8 1.27E+8 1.27E+8 1.27Ee8 1.27E*8 1.27E+8 1.27E*8 1.27E*8 Xe-135m 3.26E+7 3.26E+7 3.26E+7 3.26E+7 3.26E+7 3.26E*7 3.26E47 J. 26 Ee 7 3.26E*7 3.26E+7 3.26E+7 Xe-135 2.09E+7 2.09E*7 2.09E+7 2.09E+7 2.0 9 E+7 2.09E*7 2.09Ee7 2.09E*7 2.09E+7 2.09E*7 2.09E*7 Xe-138 1.17E*8 1.17E+8 1.17E*8 1.17E*8 1.17E+8 1.17E+8 1.17E*8 1.17E*8 1.17E*8 1.17E*8 1.17E*8 I-129 9.00E-1 9.73E-1 1.06E*0 1.15E+0 1. 2 4 E+ 0 1.33E+0 1.42E*0 1.51E*0 1.60E*0 1.71E+0 1.80Ee9 I-131 3.09E+7 6.89E+7 7.32E+7 7.35E+7 7. 3 5 E *7 7. 3 5E* 7 7.35E*7 7.35E*7 7.35Ee7 7.35E*7 7.35E+7 I-132 5.05E+7 8.61E*7 8.62E+7 8.62E+7 8.62E*7 8.62E+7 8.62E*7 8.62E*7 8.62E*7 8.62E*7 8.62E*7 I-133 1.22E*8 1.28E+8 1.28E+8 1.28E+8 1. 28 E* 8 1.28E*8 1.28Ee8 1.28E*8 1.28E+8 1.28E*8 1.28E*8 I-134 1.60E+8 1.60E+8 1.60E+8 1.60E+8 1. 6 0 E* 8 1.60E+8 1.60E*8 1.60E+8 1.60E*8 1.60E*8 1.60E*8 p I-135 1.27E*8 1.27E*8 1.27E*8 1.27E+8 1.27E*8 1.27E*8 1.27Ee8 1.27Ee8 1.27E*8 1.27E*8 1.27E*8 o Cs-134 4.88E+5 5.37E*5 5.98E+5 6.63E*5 7.33E*5 8.07E+5 8.85E*5 9.67E+5 1.05E*6 1.17E*6 1.27Ee6

$ Cs-136 3.19E+5 6.82E+5 7.78E*5 7.98E+5 8.01 E* 5 8.02E+5 8.02E+5 0.02E+5 8.02E+5 8.02E*5 8 32E*5 m CS-137 2.52E+6 2.73E*6 2.98E*6 3.22E+6 3.4 6 E+ 6 3.71E*6 3.95E*6 4.19E*6 4.43E*6 4.75E*6 4.99E*6

@ Cs-138 1.23E+8 1.23E+8  ?.23E+8 1.23E*8 1. 23 E+ 8 1.23E*8 1.23Ee8 1.23E*8 1.23E+8 1.23E*8 1.23E*8 G Ba-137m 2.36E+6 2.56E+6 4.78E+6 3.01E*6 3. 24 E* 6 3.47Ee6 3.69E*6 3.92E*6 4.14E*6 4.44E*6 4.67E+6

-s Ba-140 5.73E*7 1.09E*8 1.22E+8 1.25E*8 1.25E*8 1.25Ee8 1.25E*8 1.2SE*8 1.25E*8 1.25E*8 1.25E*8 t; La- 14 0 5.18E+7 1.00E+8 1.23E+8 1.26Ee8 1. 27 E* 8 1.27E*8 1.27E*8 1.27E*8 1.27E*8 1.27E*8 1.27E+8 Ce-144 4.51E*7 4.86E*7 5.24E+7 5.59E*7 5. 91 E+7 6.21E+7 6.49E*7 6.75E*7 7.00E+7 7.29Ee7 7.50E+7

MIDLAND 1&2-FSAR TABLE 2.3-28 .

SHORT-TERM (X/Q) VALtJES EVALUATED AT 300, 500, AND 1,600 METERS1975 ANDTO 10,FEt$RUARY 30, AND 5028, MILES FROM 1977)

THE SOURCE (MIDLAND NUCLEAR PROJECT, DATA PERIOD MARCII 1, (units in s/m a)

Averaging Arithmetic First Fifth Fiftieth Distance Interval from Source (houtu) Worst Case Percentile Percentile Percentile _ Mean 1 0.2566E-01 0.3730E-02 0.1260E-02 0.1500E-03 0.3612E-03 30D meters 0.2837E-03 2 0.2566E-01 0.2830E-02 0.9680E-03 0.1269E-03 0.1327E-01 0.1609E-02 0.7043E-03 0.9638E-04 0.1997E-03 8 0.1213E-03 16 0.3317E-02 0.7375E-03 0.2989E-03 0.b093E-04 0.7598E-03 0.4198E-03 0.2011E-03 0.5702E-04 0.7751E-04 72 0.4583E-04 624 0.1141E-03 0.1125E-03 0.9183E-04 0.3804E-04 0.1062E-01 0.1632E-02 0.5908E-03 0'.9423E-04 0.1857E-03 l 520 meters 1 2 0.1062E-01 0.1198E-02 0.4494E-03 0.7627E-04 0.1448E-03 0.5503E-02 0.7041E-03 0.3042E-03 0.5818E-04 0.1005E-03 8 0.4831E-04 16 0.1320E-02 0.2909E-03 0.1189E-03 0.3204E-04 0.3022E-03 0.1672E-03 0.7996E-04 0.2260E-04 0.3086E-04 72 0.1821E-04 624 0.4534E-04 0.4473E,04 0.3658E-04 0.1513E-04 ~

l 0.2869E-02 0.4321E-03 0.1777E-03 0.1648E-04 0.4397E-04 1,6f0 meters 1 0.3449E-04 7 2 0.2869E-02 0.3242E-03 0.1308E-03 0.1354E-04 0.1499E-02 0.1901E-03 0.8486E-04 0.1093E-04 0.2433E-04 8

16 0.1843E-03 0.3887E-04 0.1637E-04 0.3933E-05 0.6249E-05 0.4203E-04 0.2286E-04 0.1076E-04 0.2915E-05 0.4054E-05 72 0.2414E-05 624 0.6137E-05 0.6048E-05 0.4975E-05 0.1971E-05 1 0.2255E-03 0.3290E-04 0.1112E-04 0.6467E-06 0.2563E-05 10 ciles 0.5406E-06 0.2035E-05 2 0.2255E-03 0.2459E-04 0.0510E-05 8 0.1167E-03 0.1411E-04' O.6090E-05 0.4652E-06 0.1470E-05 16 0.6895E-05 0.1450E-05 0.6043E-06 0.1241E-06 0.2158E-06 72 0.1563E-05 0.8385E-06 0.4025E-06 0.1007E-06 0.1426E-06 624 0.2218E-06 0.2194E-06 0.1832E-06 0.6873E-07 0.8584E-07 l 0.5447E-04 0.7708E-05 0.2646E-05 0.1349E-06 0.5956E-06 30 ciles 1 0.1133E-06 0.4735E-06 2 0.5447E-04 0.5920E-05 0.2026E-05 l

8 0.2816E-04 0.3332E-05 0.1443E-05 0.1008E-06 0.3432E-06 16 0.1443E-05 0.3030E-06 0.1262E-06 0.2416E-07 0.4365E-07 72 0.3263E-06 0.1750E-06 0.8427E-07 0.2037E 0.2909E-07 624 0.4603E-07 0.4546E-07 0.3809E-07 0.1398E-07 0.1762E-07 3

0.2791E-04 0.3950E-05 0.1336E-05 0.6499E-07 0.3000E-06

f. 50 ciles o

1 2 0.2791E-04 0.3032E-05 0.1038E-05 0.b463E-07 0.2400E-06 0.1708E-05 0.7403E-06 0.4938E-07 0.174aE-06 f

J 16 8 0.1443E-04 0.6976E-06 0.1464E-06 0.8444E-07 0.6096E-07 0.4073E-07 0.1131E-07 0.9715E-08 0.2078E-07 0.1396E-07 72 0.1576E-06 624 0.2216E-07 0.2188E-07 0.1835E-07 0.6655E-08 0.0462E-08

[7 Table 2.3-28 NOTE: E-06 = 10 Revision 7 3/78

.m..--. .- . . . . .....-._._____.__.w

MIDLAND 162-FSAR TABLE 15.6-10 PARAMETERS USED IN EVALUATING THE RADIOLCGICAL CONSEQU7NCES OF A LCSS-OF-COOLANT ACCIDENT Ccnservative Realistic Parame*ar Analysis Analvsis Source Da-a Power level, MWt 2,552 2,552 Fraction of core activity initially airborne in :ne containment, percent Noble gas 100 100(13 Io. dine 25 25C*3 Activity Release Data containment leakage rate, volume percent per day 0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.10 0.10 1 to 30 days 0.05 0.05 Fraction of containment leakage that is unfiltered, percent 100 100 Credit for containment spray system Decontamination factor s Elemental 100 100 18 Particulate 100 100 Iodine spray removal constants, hr-1 Single region See Table 15.6-9 Effective two region Elemental 4.05 4.95 0 0 18 Organic, 0-2 hr 0.333 0.333 Particulate (sheet 1)

Revision 18 2/79 Enclosure (1)

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s aut w a w w .J w .4 e 3 . as a: 3 a o

% u M eS N O d d e' N@ eM . i 2'! O m2 4 *e at 4 **4 *3 O i.e 3 O ia Q L 6.4 Ig e N Pm w e =0 e ** @ e' e d '

l , O ** a. Q = Q Q Q. O Q. O Z w Q Z =e.

i.,e 2u *= = *=' P* 8'1 ** i a se M i e eeO e ** E wa 43 4 43 43 > G3 D= 2 in. = 6 n.A

>= == ned %G G @ d 0 8 e3 5 9s eop e  !' l t om *E ** E Q , E E aC E aE e4 ** 4 == M Z

.4 O w E en a tad 1.4 m tad we o e r *EJ > e' 4 G3 4 4 m3 4 E 43 u se Q e ce Q Q s=

M. P. ce e M.* O a: n .4 E e p o ,o 4 e ,e P= e e r- * ,  !

w p= *4 a .J a. a a.

e e un e ws i.J e w w w w waw d .= 2 .J N e N M e en O O *a e P= i n.m p= e= e >=

M .* N s') e e o e e. $ es e F1 i srl . >= >= 9 G A me. 4 e == M ** >= - >= >=

= > = . an e eesrl e e M Ms u.a e O * ,  ; 0@ e.= at

  • 8= * *=* *=
  • e ' *= e at erl as P= 4 as at 4 O as L.4 e e s= ce w e ee e o Nno e we 5 8 cas i .J a. e a. =sa e 5 4 I P1.J u .J u .J .J d .J == J l 3I3 N e.e w4
  • e e ee tas N @ e@eOGQ -

44 e >= 3Aw >aC==*>=**>=3 3 3 3 3 u WNuuu

s. e N.N o O.e ac w4.Ja.asQa.a.eso.e ue u s>u

-= a EO a o o. OeweM i i w.

4 4wP= e .- e N ew

' l n i.a - 4. a a e . 4 a a x = -e = w .A O-e4 e w a. r i w m w a. . N 4 ,.3 4 e 4 Q 4 e 4 ,J 4

.J .4 .J -e aJ Q a e a m Q M N e ,,.O , o P= O,

-2

- w ,3 e%M oO.  %

4 =.,. eN e.Mm, e . .e I. . P= nM. ~e O -u-o wi e e e emuuuuuuue udu-u w a - o l a. u E % an e 8% e e. e. .eOO ei - =- w s o 4 a.a O- 24edecoaN e .e.e O O. e M.e o. e e o Q Q e.n . a.ee. , ee u e. e % %. O e e. e e e si e O O -

C O .4 *E 23 e *E o e % E % P. N et e e e e e P= 18 teiO M we O O *" O e @ e G *e me Z am W me .'Da 4.3 ** *e' at N e' e =E G M % 19 1 O ** GB sd3 8Fl - ** em @*O O O O O O O O se f 4 e Z Z u em 2 G3 M e 1.&48 9 0 .J 8 0 0 .J G eO 4 ert N N el 8'1' e ' e ned A. es ee e e e e o e e u , u u ed u ==

  • == s.a 2e 4.A L.de I.J w t.s e e'ee > D= l.a O et 10 et 11+ 60 18 le 18 le el la at. le

at 4 n.# .J es as o r= at c >= e at d'O as O O es st i se te to ' et 4 414 s= se It' #4 e E Ea E 4 >= e= cm e e= ee M p == >= P= >= me me at a v3

C == N M e if1 *O P= w =u == 4.e at as e e at e e e 4 at.e as X Z ee N M e d W Q.Q O E Q ce N art e d 4 P== e 04 4 h u u u u u e.a u u O Q Q Q Q Q nas W cs Q as O Q 4 05 Q es F* M C C *e Q u u > >; > > >=' *= wt to Q :n 2 N E3 e e e e e e i e

.3 ** =E O

  • 3 M 2 in

- ee ee ,

O M - 4 i u. u 4a u u u u o u i

w 2 u a o w l i 0 - . .

e -

N a. 4.s N arg e it) 4 P=

e Q N srl e d 4 P. e e O -e N srp e 40 wG P= e 95 O se N fr> e 4f1 90, P* ft O **

  • e OOOO O O O' O w. .e.e.e== e**coesce N ce N N ew es N N p1 at art srt M M M wi 2 c3 c3 Q O O O O O Q Q O O O O O O Q s= QOOO O O O. OC00000000000 O O O OC00 O O Ce OOOOOOOOCOOOO O OOOOOOOOO O C3 O 2 and o >= wt 2 Z 2 2 2* 2 2 2 2 2 2 2 2 2 2 2 en 2 2222 2 2 22222222'22222 en 2',

WP en in in M wn wP v3 vs en W5 en wt en wemeweemne to en en en em wt en w wt wt o M en M we en we me me.

we

p. en me we me se se oe me ma mag me me wt me ** ** me me me me me me se me se se me me we 2 3 me memememe me t.4 3 *=

3i8 4.d a. , l 8 4 Q n

:.nclosure (1) v,r, e c. .

. . .. . .. . .-.a

. . .e 1' ., .* *. 2 A +

- r .

e e . *

. . a.

a o a *

/*'m D

  • 3

'1 CAMMA 00$E ikOM ICDlh[

l' r - - -

I ~

ISOTOPE 1 DOSE 7.4040E-01 .

ISOTOPE 2 00$[ 2.5337E*00 , ...

IS0TCPE 3 DOSE 1.7560E*00 i ISOTOPE 4 DOSE 3.4256[+00 e 150 TOPE 5 00$[

3.4275Et00 - .

'; ISOTOPE 6 Dose 1.8064E-01 I TOTAL Dose 15 = 1.2064E*01 p 4 GAMMA DOSE Fh0M h0BLE CASES u

  • "i L ISOTOPE 1 00$E 6.0516E-03 4

15010PE 2 DOSE 1.9308E+00. - . .. __..._- ._ - _. . . .. I

ISOIOPE 3 DOSE 1.5802E-03 ISOTOPE 4 DOSE 4.3811[+00 ISOIOPE 5 DOSE 3 9296Et01 . .- - _ - _ _ _ _ . ..

'! ISOTOPE 6 00$E 0.0 l

' ISOTOPE 7 00$E 0.0  !

ISOTOPE B DOSE 0.0 - . . .. . - - _I

+

ISOTOPE 9 DOSE 0.0 15010PE 10 DOSE 0.0 ..

IS010PE 11 DOSE 0.0 _. ._ .. .

IS010PE 12 00$E 1 9000E-03 __.I

' ISOIOPE 13 00$[ $.0884E-02 9

. 150 TOPE 19 005E 4.9809E*00 _ . . . -_ _.

.._.___..-_-_..___..-_.I, IS0iOPE 15 DOSE 7.2952E-02 ISOTOPE 16 03SE 4.3159E*00 i

' ~

ISOTOPE 17 00$E 00 . _ . . _ .. . .._...-?_. . _ , ,

"I ISOTOPE 18 00$f 4.3054E-01 l ISOTOPE 19 00SE 0.0 .

ISOTOPE 20 Dose 0.0 _. . . . _ . _ _ _ . ..-._._-.-!

  • ISOTOPE 21 DOSE 0.0

, ISOTOPE 22 DOSE 1.2701E*01 .

i ISOTOPE 23 DOSE 4.54 FEE +00 __ _ . . _ ., ..

, TOTAL DOSE 15 = 7 2757E*01

[

1 -

gq . - . >

X

'O  !

^

s.

?

e'

ISOTOFE LIST Iodine Doses Isotope No !sotope 1 I-131 2 I-132 3 I-133 h I-134 5 I-135 6 3r-Sh Noble Gas Deses Isotore No Isotore 1 Kr-83=

2 Kr-85m 3 Kr-85 h

Kr-87 5 Kr-88 6 Kr-89 7 Kr-90 8 Kr-91 9 Kr-92 10 Kr-93 11 Kr-9h 12 Xe-131=

13 Xe-133=

1h Xe-133 15 Xe-135m 16 Xe-135 17 Xe-137 18 Xe-138 19 Xe-140 20 Xe-lkl 21 Xe-lh3 22 Bb-88 23 Cs-138 Enclosure (1)