ML20212D941

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Rev 9 to Offsite Dose Calculation Manual. Marked-up Rev 9 to Manual Encl
ML20212D941
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/28/1986
From: Rolonda Jackson, Mckay J, Megan Wright
MIDDLE SOUTH UTILITIES, INC.
To:
Shared Package
ML20212D758 List:
References
PROC-860828, NUDOCS 8703040237
Download: ML20212D941 (16)
v • d • e


Text

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ATTACHMENT IV OFFSITE DOSE CALCULATION MANUAL REVISION NO. 9' E

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OFFSITE DOSE CALCULATION MANUAL i GRAND GULF NUCLEAR. STATION ,

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l GRAND GULF, UNIT 1 Rev. 9 - 08/86 J200DCN86081902

_ . . ~ - _ . ~ _ _ , . . ~ . . _ . . - - _ . . _ , _ _ _ . _ _.._ .._... .-..__. _ _ _._.._._,_..__-.._... _ _ _ ._ __._ _ ...___.. _ _.

l Revision No. 9 Date 08/86 _

GRAND GULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL SAFETY RELATED EVALUATION APPLICABILITY ENVIRONMENTAL EVALUATION SAFETY EVALUATION

[X] APPLICABLE

[X] APPLICABLE

[ ] NOT APPLICABLE

[ ] NOT APPLICABLE Reviewed / Approved: do . She 8- 2 l

  • E (o ntal Services /Ds;.e Supervisor, Envi Reviewed / Approved: A M ,c % h M.2. 8e// 2/[1iirf.

Supervip6r, Radiological St.; vices /Date Reviewed / Approved:

Manager,Radiologicp&EnvironmentalServices/DateAUG 211986 Reviewed / Approved:

4 / '

rector, Nuclea Sport /Date

'"~

h Reviewed / Approved: jtliairman, PrahtV9e' fat /fReview Committee /Date U

GRAND GULF, UNIT 1 i Rev. 9 - 08/86 86081902

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.ODCM L

LIST OF EFFECTIW. PAGES- ,

PAGE REV.

PAGE REV.

NO. NO. 1

.NO. NO._

+

1 9

2.0-22 i 2.0-23 7 ii 2 6 8 ~ 2.0-24 iii 2.0 0 iv 8 7_

6 2.0-26 v 2.0-27 3 vi 2 5 9 2.0-28 vii 2.0-29 3 2.0-30 3 3 1,0-1 0 0 2 2.0-31 i,0-2 0 2 2.0-32 1.0-3 2.0-33 0 .. '

1 1.0-4 2.0-34 ~0 1.0-5 9 8 1 .2.0-35 1.0-6 2.0-35a 8 1.0-7 5 i 2.0-36 8 '.

1.0-8 8 8 2 2.0-37 '

1.0-9 1.0-10 0 6 0 3.0-1 1.0 3.0-2 6- t t

1.0-12 0 7 2 3.0-3 1.0-13 3.0-3a 7 1.0-14 1 6 8 3.0-3b 1.0-15 3.0-4 6 1.0-16 8 5 l 3.0-5 3.0-6 5 2.0-1 5 5 5 3.0-6a l

2.0-2 3.0-6b 5 2.0 2 6 6 3.0-6c 2.0-4 3.0-7 3 2.0-5 6 1 0 3.0-8 2.0-6 3.0-9 3 2.0-7 5 5 l 6 3.0-10 l

-2.0-8 3.0-11 5 2.0-9 6 2.0-10 5 l 8 2.0-10a 2.0-11 1 l4- 2.0-12 1 2.0-13 2 2.0-14 1 2.0-15 2 2.0-16 2 2.0-17 1 2.0-18 2

( 2.0-19 1

!. 1 l

2.0-20 2.0-21 2 GRAND GULF, UNIT 1 vii Rev. 9 - 08/86

-J200DCM86081902 - , _ - _ - ,

p.

P 9-Thus, if instrumentation indicates the dilution flow rate falls. ~ ^

45 below the assumed flow rate of 90 percent of the actual dilution .t q-

. flow, or-if the waste tank effluent flow rate exceeds-90 percent  %

h 9 ,;

of the calculated maximum vaste tank effluent flow rate, t e i:

c

-release'is' terminated (manually or automatically).

-Step 5) The radioactivity monitor setpoint may now be specified. based on the values of ICg, F, and f which were specified to provide ,

' compliance with the limits of 10CFR20, Appendix B, Table.II,

]' ,

Column 2. The menitor response is'primarily to. gamma radiation; therefore, the actual setpoint is based on 8I C8 . The setpoint . , .

- fi .

concentration, C,is determined as follows:

I d

C = -

Ig C g (uCi/al) ,

a f (7)

, a

~l where f, is the actual.(or maximum expected) waste tank effluent flow rate. The value of C,(uCi/ml) is w.ed to determine the

(

i monitor.setpoint (CPM) frcm the calibration curve of Figure 1.0-1.

NOTE:

The setpoint contains a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the l

calculeted rate contains the safety factor margin, waste taak In effluent flow rate margin, and the dilution flow rate margin.

practice, the actual waste tank effluent flow rate normally is many, times less than the calculated tank flow rate, thus providing an additional conservatism during release.

l l

)

GRAND GULF, UNIT 1 1.0-5 Rev. 9 - 08/86 l 'J200DCM86081902 .' "**~*"'"*=e---avg.,_ , _ _ _ , ,

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ATTACHMENT V!

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^' 0FFSITE DOSE CALCULATION MANUAL REVISION NO.'9.- MARKUP _

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- f- d the waste tank effluent flow setpoint as measured at the

~

radiation sonitor 1ccation, in volume per unit time, but i

.m .

in the sane units as F, below.

the F = the dilution water flow setpoint as smasured prior to release point, in. volume per mit time.

At Grand Gulf Unit 1, the available dilution water flaw (F) .

should be constant for a given release, and the wasta tank ficw (f)

,' and sanitor setpoint (c) are,, set to meet the condition of equation The method by dich this 1 for a given effluent ccmcentration, C.

is accorplished is as follows:

Stap 1)

The isotopic concentration for a waste tank to be released is ebtained frm the se of the ---1M wwd. rations as detar mined by the analysis required in the RErs Table 4.11.1.rl.1-1:

(2) -

Cg = C + C, + C, + Cg 9

+C f where: ,L. j

= the sun of concentrations C, of each naasured

{C9 gama emittar observed by gama-ray spectroscopy of the waste sangle.

gross_ j[

ef the concentratidc*falphaemittersin a 4 SC, =

i -

liquid waste as sensured in the acnthly mita sample.

[c, = the suasured wwtratiens of Sr-89 and Sr-90 in liquid waste as observed in the quartarly acr.posita sanple.

/

t ( Dev. 2 - 5/84 GMC GET, UhTI 1 1.0-2 n ' ' _ _ - - - - _ _ _ _ _ . . . - - _ _ _ _ _

I!

. ~ ,

I  ;

( = the sma a ed concen eatim of 5 3 in liquid wasta as 1

'- Cg -j,

g. .

detezzcined fra analysis of the sonthly =,-site 1-

.g 4 y_

sanple.

[,

y be u

l j y (3 .She C , term will be included in the analysis ofm each vasta

- as< A l tank batch to be reina Ar terms for alpha, stror}tims,# i-

  • 3, J o3  !-

S <

3 ex 5 (k u s a[ tritih be included if analysis of zanctor water the presence of these isotopes.

QJ 4j .

gL stap 2)- the inmasured radieclida can'omntratices are used to calculat a Dilution Factor, D.F., which is the ratio of total dilutien l3 0 .3 L ,

iu-3 ,

flow rate to wasta tank effluent flow rata required to assure -  !!

d

~

b =J that the limiting concentration of 10CFR20, Appendix B, Table o

i g 2p l u ae II, Colum 2 are net at the point of discharge. ___

s ,2 "g l c

, l ,-

f

[< u I D.F.

1 f (3)

/ (7 Ce C, , C, , Ct'[

+[(. "a t (, s

  1. t and c f Where:

Cf = C , C,, C,, Mc[ naasured(ocacentrations as 9

defined in Step 1. Terns C,, C,,MC)will be and MPC

{- included i' the cal M atien as appropriata.

f

  • j t r sc i - mC,,pl C,, .sermCjm umiting c=c=ntra-tions of the appropriate radianuclide frtzn 10CFR20, i

l Appendix B, Table II, Colm n 2.

For dissolved or l

entrained noble gases, the concentration shall be limited l to 2. 5-4 UCi/mi total activity.

s 1

1.0-3 Pev. 2 - 5/84 GRAND GUIF, UNIT 1

. . . . . . = .~ . -.

l Thus, if instrumentation indicates the dilution flow rate falls

-below the assumed flow rate of 90 percent of the actual dilution flow, or-if the waste tank effluent flow rate exceeds 90 percent _

of the calculated maxiraum waste tank effluent' flow rate, the' g release is terminated (manually or automatically). ~

i Step 5)- The' radioactivity monitor setpoint may now be specified based on' the values of IC , F, and'f which were specified to provide -

3g g

compliance with the. limits of 10CFR20, Appendix B, Table II, Column 2. The monitor response is primarily to gamma radiation; ,

therefore, the actual setpoint is based on I 8 C. The setpoint  ;:

l 8 concentration, C,it determined as follows:

C = I C

" f 8 8 (uCi/ml) (7) -

a ,

t i where f,'is the actual (or maximum expected) waste tank effluent flow rate. The value of C,(uci/ml) is used to determine the 2

monitor setpoint (CPM) from [ calibration curve [ igure 1.0-1.

imilarto)

NOTE: The setpoint contains a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the l

calculated rate contains

  • the safety factor margin, waste tank In effluent flow rate margin, and the dilution flow rate margin.

l.

practice, the actual waste tank effluent flow rate normally is 4

many times less than the calculated tank flow rate, thus providing an additional' conservatism during release.

4 1

GRAND.GU1I,. UNIT 1 Rev. 9 - 08/86 J200DCM86081902 1.0-5

. - - . .- - - . . . - - . - . - _ . . . - . _ . _ - . . . . - . - - . . . _ . - - _ - . - . . - - - - - ,~

[ Example }

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calibratica curvo fcr Liquid Efflusst Moniter

  • - Figura'1.0-lj .

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g-r # M k -y - ., - . . a- - - -

- _ = ~ =

m.a ..aw-r 10' g-- _ _

103 go.g 3 10

1 2 10 10 10 Count Rate (Counts par Minute) kV- 1 l 1.0-6 .

Crand Gulf, Unit 1 e

4 TABLE 2.2-3

~

CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS Origin ,. ,

Distance Ane Grous , (for info only)-. l (Meters) ** Miles Pathway Sector l Vegetation _; garden '

0.92 A4 ult - :--I' (A) N, , 1481 _ - - - _ , _ _ ___--

0.75 Vegetation. Teenagar - garden (5) ENE 1207 Vegetation Teenager

_* 12'

" - = garden.

(C) NE 1062 0.66 Ir' 1lrs' ri_z:

.~

Child 4300 2.69- Inha1/ Gad 161ane -Ee6esem= - residence (D) ENE 982 0.61 Inha1/ God Plane, Adult - residence

-(E) E 7000 4.38 Inha1/ God Plane Adult - residence ,

(F) ESI Child 3100 1.94 Inha1/ God Plane h - residence (G) SE .

1800 1.13 Inha1/ God Plane Adult - residence (H) SSE '

805 0.50 Vegetation Child - hypothetical * ,

(J) S '-

3734 2.33

-ib 488- Vegetation Child - garden

, (E) SSW -46eGE 1432 0.90 Inha1/ God Plane Adult - residence-(L) SW 8047 5.00 Cow / Milk Infant - hypothetical ,

(M) WSW 8047 5.00 Cow / Milk Infant - hypothetical (N) W Vegetation 7680 -4.80 -- "- --- garden i

Child (P) WNW 46664.

8047 5.00 Cov/ Milk Infant - hypothetical (Q) NW 0.75 Vegetation Child - hypothetical *

(R) NNW 1207 c

6 Tablebasedon198[LandUseCensus ,

  • These locations represent MP&L gardens located'inside the site boundary.

4

    • Distances shown are ectual mileage in each sector.

i t

.k GRAND GUII, UNIT 1 2.0-23 Rev. 7 - 6/86 J36PMI86063001 - 6

,,. ~.,e.,.__,,.,___,...,-,,..,--..,,~,..,,...,,,,_,_w -,.__,,r, ,-_,,,,,...._,..m,. ,,,m., ,-,,,_.m.-,~ ,-,,e

e 2.3 Meteorological Model 2.3.1 The atmospheric dispersion for gaseous releases may be

- calculated using a ground-level, wake-split form of the straight line flow model. ,

3 I/Q . = atmospheric dispersion (sec/m )

2.03 6 k ru I

- Where, r s. distance (a) from release point to location of interest

~

6 = plume' depletion factor at distance r from Figure 2.3-1.

u = wind speed at ground level (m/sec) k = open terrain recirculation factor at distance '

i r, from page 2.0-34 I = the lesser of (cz + b_2) % or 43o Where, o = vertic1[standarddeviation(m)oftheplumeat distance r for ground-level relegses under the stability category indicated by T, from Figure i

2.3-2.

T = temperature differential with vertical separation

(*K/100m)

{'

b = height of the reactor building = 53.3m.

L 2.0-24 Rev. 6 o/85 GRAND GUII, UNIT 1 J200DCM850829

TABLE 2.3-1 f

ATHOSPHERIC DISPERSION PARAMETERS

0.92 1.333 x 10-8 5.485 x 10-'

'(A) N 0.75 1.129 x 10-8 5.298 x 10-'

(B) NNE (

O.66 9.373 x 10-7.,,, 5.821 x 10-'

(C) NE 2.69 7.358 x 10-s 4.341 x 10-10 (D) ENE 0.61' 8.618 x 10-7 5.135 x 10-'

(E) E 4.38 3.206 x 10-s 1.824 x 10-10 .

(F) ESE 1.94 2.628 x 10-7 1.474 x 10-'

(G) SE 1.13 7.347 x 10-7 3.587 x 10-' .

(H) SSE j 0.50 4.057 x 10-8 1.408 x 10-s

~

(J) 5 4

0.90 2.653 x 10-8 4.463 x 10-'

(L) SV 5.00 3.931 x 10-7 3.177 x 10-10 (M) WSW 5.00 4.259 x 10-7 3.746 x 10-10 (N) W 4.80 4=63.a. 3.164 x 10-7 3.739 x 10-10 (P) WNW 5.00 1.584 x 10-7 2.733 x 10-10 (Q) NW 0.75 2.199 x 10-s 7.650 x 10-8 (R) NNW

Reference:

Grand Gulf Nuclear Station, Final Environmental Report, Table 6.1.26, 6.1.28, 6.1.29 and ODCM Table 2.2-3.

In those cases where X/Q

    • Distances shown are actual miles in each sector.

and D/Q were not available from FER Table 6."1.26, they were taken from FER Tables 6.1.28 and 6.1.29 using the closest distauce interval to the plant.

s -

_______L - _-

-10 2.33 4.022 x 10"I 8.232 x 10 (K) SSW

_=-

= z ,__ __

( -

GRAND GULF, UNIT 1 2.0-26 Rev. 7 - 6/86 J36PMI86063001 - 7

2.6 Anndal Dose Commitment .,

  • For the purpose of implementing Technical Specification 3.11.4, the annual (calendar year) dose or dose commitment to any MEMBER OF THE FUBLIC will be calculated by summing the following doses for the calendar year:
  • Direct radiation dose
  • Liquid effluent dose (DTau) .

  • Noblegasdose(D,Dh)*
  • Particulate dose (D,)

These calculations are required only if the liquid or gaseous affluents exceed twice the limits of Technical Specifications or 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a a t

3.11.2.3.b.

2.6.1 Direct Radiation Dose Measurement Technical Specification 3.11.4 requires the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable only under conditions set forth in Specification 3.11.4 Action a. This determination is made by the utilization indicator} '

~~

ofdirectradiationmeasurementsfroakthermoluminescent dosimeters (TLDs) M -5 2 th:;23 % S'Nocated g  :' - ," * - -^ -

irt rr :1: rr th: '.'rit I s;::t::t:f :::: L;;;. In::t"-

==

_~~-__

near the CGNS property line in each of the 16 meteorological sectors. _e s 2.0-36 Rev. 8 - 08/86 GRAND GULF, UNIT 1 J36PMI86052201 - 12

f 1::: tics: :::

f:'in:f in T;il; 2.0 ? Measurements from .

these TLDs represent the direct radiation generated by the F facility plus normal background radiation.c .

Control TLD's are also utilized to differentiate between background radiation and direct radiation from the .

facility. The following seven TLDs are designated as

~~ controls based on the criterion that they are located ten miles or greater from the facility. Exact locations are identified in Table 3.0-3.

M-12 M-14 M-39 M-06 M-11 M-13 M-33 4 The difference between the averaged quarterly radiation 5

indicator

_ J measurements of the ; :t::t:f x:?TLDs and the control TLDs represents the direct radistion dose to a MEMBER OF TE PUBLIC from the operating facility. i l k f'

The locations are identified in Table 3.0-3 by the following TLD numbers:

H.41' M-86 M-16 M-22 i

M-13 M-25 M-42 N l

M-44 M*93 M-19 M-27 i

~

M-45 M-94 M-21 M-28 n- --~ ^= =

2.0-37 Rev. 8 - 08/86 GRAND GULF, UNIT 1 J36PMI86052201 - 37

e r%

' ODCM TABII 3.0-3 (CONTINUED)

TLD LOCATIONS '

Page 6 of 6 FIGURE SECTOR MILE TLD NO. LOCATION Midway of North fence Not M-74 Shown P Onsite M-75 Corner in fence in front " A of Maintenance Shop . .e, .e, so n "h

" A M-76 Southeast corner SSW Basins-M-77 Protected area fence beside " R "j O i

maintenance shop Q

"- k 7 M-78 Outside vault in Admin. Bldg. j ,

i :1

" " e e e ,

Q $

M-79 Wall in Central Records (middle) 5 $

M-80 Wall in Central Records old " "

{'Ng N'N g g library location Q m z f r.

g 1

i Inside Admin. Bldg., 2nd floor, k

M-81 northeast vall Q "f

{'.

" Q M-82 Tech. Support Area ' .

Tech Support Secretary's office Q M-83 P

M-84 Security Island t e l Lee Electric Building Across .,

3 m 6 M-85 from Port Gibson High School 3.0-3 G 5.2

'O 3 l Bechtel Gate North Site 5 .$u $ j

  • M-86 ** 3.0-1 B 0.5 i .,  ?

Boundary I i 3 I g g M-87 Intersection of Rodney Road

& transmission line 3.0-3 J 3.5 $ eN ew 8 t 3 '

  • M-88 River mile marker 409.5 3.0-1 A 4.2 y g

m m t

i 3.0-1 R 4.4 ,

  • M-89 Middle Ground Island '

n m .e ,

3.0-1 Q 3.5 ,T T T i

  • M-90 Across from Middle Ground Island z z z Transmission line by pond 3.0-1 J 4.5
  • M-91 9  %.

A'

  • Technical Specification requirements GRAND GUII, UNIT 1 3.0-6c Rev. 6 - 9/85 ,

1 J200DC".850829

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