ML20212D800

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Rev 8 to Offsite Dose Calculation Manual. Marked-up Rev 8 to Manual Encl
ML20212D800
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/25/1986
From: Rolonda Jackson
MIDDLE SOUTH UTILITIES, INC.
To:
Shared Package
ML20212D758 List:
References
PROC-860825, NUDOCS 8703040207
Download: ML20212D800 (14)
v • d • e


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Revision No. 8 ,

Date ~08/86 5

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

[X] APPLICABLE [X} APPLICABLE  ;

I

[ ]-NOT APPLICABLE [ ] NOT APPLICABLE Reviewed / Approved:

. c-b- h 8 U Supervisor,EnvignmentalServ' ices /Date-Reviewed / Approved: M , ws /w ,(g - M./.. /7e// M/7/1FTe t

Supervisor, Radiological Services /Date 20M f ' Reviewed / Approved:

Manager, Radiological &EnvironmentalServices/Date Reviewed / Approved: N '

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Director, Nuc apupprt/Date kf w i/ 2-Reviewed / Approved: [.

Chairinan', TfariDSafg Revi T Oommittee'/Date I

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

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ODCM TABLE OF CONTENTS

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MANUAL APPROVAL SHEET .......................................... i 4_ . .

1 INTRODUCTION ................................................... i1 .

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TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii 4 LIST OF F IGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .'. . . . . . . . . . . . . . . . . . iv LIST OF TABLES ................................................. v LIST OF REFERENCES ............................................. vi s LIST OF EFFECTIVE PAGES ........................................ vii ';

I 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.0-1 1.1.1 . Liquid Radwaste Effluent Line Monitors .........

1.2 Dose Calculations for Liquid Effluents- 1.0-7 1.2.1 Maximum Exposed Individual Model ............... 1. 0-8 8 1.2.2- Do s e P roj e ction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.0-15 1.3 . Liquid Radwaste Treatment System .........................  ?

2.0 GASEOUS EFFLUENTS 2.1- Gaseous Effluent Monitor Setpoints 2.0-1 2.1.1 Continuous Ventilation Monitors ................ 2.0-3 2.1.2 Text Deleted ...................................

2.2 Gaseous Effluent Dose Calculations 2.2.1_ Unrestricted Area Boundary Dose ................ 2.0-7 2.2.2 Unrestricted Area Dose to Individual ........... 2.0-8 2. 0-10a 8 2.2;3 Do s e Proj e c tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2.3 Meteorological Model 2.0-24

-2.3.1 Atmospheric Dispersion .........................

2.0-25 2.3.2 Deposition ..................................... 2.0-27 2.4 Definitions of Gaseous Effluents Parameters .............. 2.0-35 '

2.5 Gaseous Radwaste Treatment System . . . . . . . . . . . . . . . . . . . . . . . . 2.0-36 2.6 Annual Dose Commitment ................................... 2.0-36 8 2.6.1 Direct Radiation Dose Measurement ..............

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.0-1 3.1 Sampling Locations .......................................

iii Rev. 8 - 08/86 GRAND GULF, UNIT 1 J36PMI86052201 - 5

.l-6 O _DCM LIST OF FIGURES Page Title 4 Figure Monitor...................

1.0-6 1.0-1 Calibration Curve for Liquid Effluent 8

1.3-1 Liquid Radwaste Treatment System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-16 2.3-1 Plume Depletion Ef fect for Ground Level Releases . . . . . . . . . . . . . . . . 2.0-31 Plume.............. 2.0-32 2.3-2 Vertical Standard Deviation of Material in a Relative Deposition of Ground-Level Releases. . . . . . . . . . . . . . . . . . . . 2.0-33 2.3-3 2.3-4 Open Terrain Recirculation Factor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-34 2.0-35a 8 System...............................

2.5-1 Gaseous Radwaste Treatment Collection Site Locations , 0-5 Mile Area Map. . . . . . . . . . . . . . . . . . . . 3.0-7 3.0-1 3.0-8 3.0-2 Collection Site Locations, General Area Map.....................

Map................... 3.0-9 3.0-3 Collection Site Locations, 0-10 Mile Area 3.0-10 3.0-4 Deleted.........................................................  ?  !

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-i iv Rev. 8 - 08/86 GRAND GULF, UNIT 1 J36PMI86052201 - 5

t ODCN LIST OF EFFECTIVE PAGES.

PAGE REV.

- PAGE . REV.

NO. NO.

NO. NO.

2.0-22' 1'

'i ' 8 2.0-23 7

- 11 '2 -

2.0-24' 6 '

iii 8 2.0-25 0 iv- -8 2.0-26 7 v.

6 2.0-27 3 vi~ 2.

- 2.0-28' 5

, vii 8 C 2.0-29 3 3

1.0-1' 0 2.0-30 2 2.0-31 . 0-

- 1.0-2 0 1.0-3 2 2.0-32 2.0-33 0 1.0-4 1 0

1.0-5 6 2.0-34' 2.0-35 8 1.0-6 1 8

1.0-7 5 2.0-35a 2.0-36 8 1.0-8 -8 8

1.0-9 2 2.0-37 1.0-10 0 i '

0 3.0-1 6

' 1.0-11 6 1.0-12 0' 2.0-2 -"

1.0-13 2 3.0-3 7 3.0-3a 7-1.0-14 1 6

1.0-15 8 3.0-3b 8 3.0-4 6 1.0-16 ' -

3.0-5 5 .

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- 2.0-1 5 3.0-6 5 3.0-6a 5 2.0-2 5 -

2.0-3 2 3.0-6b 5 3.0-6c 6 2.0-4 6

,' 2.0-5 6 3.0-7 3 2.0-6 0' 3.0-8 1 2.0-7 5 3.0-9 3 3.0-10 5 2.0-8 6 5

2.0-9 6 3.0-11 l 2.0-10 5 2.0-10a' 8

! 2.0-11 1 l 2.0-12 1 l- 2.0-13 2 l' 2.0-14 1 2.0-15 2 2.0-16 2 2.0-17 1 2.0-18 2 2.0-19 1 2.0-20 1 2.0-21 2 GRAND GULF, UNIT 1 vii Rev. 8 - 08/86' J36PMI86052201 - 2 W 4 a g-*

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F =- near field average dilution factor for Cg during any 3 liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestric receiving waters times the applicable factor of 2

= average undiluted liquid waste flow average flow from site discharge x 2 5

K, = units conversion factor 1.14 x 10 0# ~

3* + 8766

= 10 ,g x 10 U = adult fish consumption (21 kg/yr) (3) ,

F BF g = Bioaccumulation factor for each nuclide, i, in fish, in pCi/kg per pCi/l from Table 1.2-1 (taken from Reference 3,' Table A-1).

DF g = Dose conversion factor for each nuclide, i, for adults in preselected organ, Tau, in arem/pCi, from Table 1.2-2 (taken from Reference 3, Table E-11).

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Calculated values of A iTau f r radionuclides which might be observed in liquid effluents are given in Table 1.2-3.

8 1.2.2 Doses from liquid effluents to UNRESTRICTED AREAS are projected at least 4.11.1.3.1.

every 31 days as required by GGNS Technical Specification i These projections are made by averaging the doses (DTau) fr a Previous operating history (normally the previous six months) which is indicative of expected future operations.

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1.0-8 Rev. 8 - 08/86 GRAND GUIJ, UNIT 1 J36PMI86052201 - 6

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j s-i 1.3 , Liquid Radwaste Treatment System-The essential components of the liquid radwaste treatment system are indicated on the following page by an asterisk (*).

8 NOTES for Fiaure 1.3-1

-(1) The essential components outlined on the following page are. ,

those necersary to collect, process and sample liquid radwaste .

prior.to discharge to the environment.

(2) Only one of the following is. required in order to process liquid wasta.

a. Equipment drain filter
b. Floor drain filter

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c. Equipment drain demineralizer
d. Floor drain demineralizer '

(3) One of the Waste Surge Tanks may be used to replace the Floor Drain Waste Collection Tank.

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particulate form over the period of interest (uCi) 1 2.2.2.c For_ the purpose of implementing Specification 6.9.1,

f of the RETS, dose calculations will be performed using or the above equations or with the substitution of average

.p meteorological parameters (most limiting parameters will-be used) which prevailed for the period of the report.

Doses from gaseous effluents to UNRESTRICTED AREAS are projected 2.2.3 t I

at least every 31 days as required by GGNS Technical Specifica-tion 4.11.2.5.1. These projections are made by averaging the 8

doses (D , Dp , D ) from previous operating history (normally p

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' 2.5' Gaseous Radwaste Treatment System The instruments required to be checked by RETS 3/4.11.2.4 to ensure that the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning are:

1. Absorber train bypass switch (IN64-HS-M611)
2. Bypass valve indication (IN64-F045)

When the absorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning.

NOTES for Figure 2.5-1 8

A flow diagram for the Gaseous Radwaste Treatment System is provided on the following page.

Notes for the diagram are listed below.

(1) The charcoal beds are bypassed during startup until an

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adequate dewpoint is obtained in the process stream.

(2) This pathway may be utilized for power levels 5 5%. 8 -

(3) Standby Gas Treatment System not normally operated.

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~2.6 Annual 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 .[

t PUBLIC will be calculated by summing the following doses for the .

calendar year:

1

  • Direct radiation dose
  • Liquid effluent dose (DTau) j.
  • Noble gas dose (D , Dp )
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  • Particulate dose (D ) 8 j These calculations are required only if the liquid or gaseous p effluents exceed'twice the limits of Technical Specifications b 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, or 1 3.11.2.3.b.

Direct Radiation Dose Measurement  ?

2.6.1 i,

Technical Specification 3.11.4 requires the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC l from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable l

i only under conditions set forth in Specification 3.11.4 Action a. This determination is made by the utilization of direct radiation measurements from thermoluminescent dosimeters (TLDs) M-61 through M-84 located at equidistant i

intervals on the Unit I protected area fence. Exact l

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GRAND GULF, UNIT 1 2.0-36 Rev. 8 - 08/86 J36PMI86052201 - 12 1

locations are defined in Table 3.0-3. Measurements from these TLDs represent the direct radiation generated by the 4 facility plus normal background r&diation.

Control TLD's are also utilized to differentiate between ,

backgrouad 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-06 M-12 M-14 M-39 M-11 M-13 H-33

  • i i-The difference between the averaged quarterJy radiation measurements of the protected area TLDs and the control TLDs represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility.  ?

MD GULF, UNIT 1 i PMI86052201 - 37 2.0-37 Rev. 8 - 08/86

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Thus, c :::t r

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I M he 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 mifthe of the calculated maximum waste tank _ effluent flow rate,.e automatically)

(manually -

release is terminated --

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Step 5)

The radioactivity monitor setpoint may now be specified based on e vide

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the values of I,01 , F, and f which were specified to pro II, compliance with the limits of 10CFR20, Appendix B, Table The monitor response is primarily to gamma radiation; Column 2. The setpoint C.

therefore, the actual setpoint is based on Ig g concentration, C ,is determined as follows:

=

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- I C C" 8 8 (uCi/ml) (7) f s 6

k effluent

(' where f, is the actual (or maximum expected) waste tan flow rate.

The value of C ,(uCi/ml) is used to determine the 1.0-1.

monitor setpoint (CPM) from the calibration curve of Figure The setpoint contains a factor of conservatism, even if the NOTE:

calculated maximum waste tank flow rate is attainable, since i ste the calculated rate contains the safety factor marg n, wa t margin.

tank effluent flow rate margin, and the dilution flow ra e In practice, the actual waste tank effluent flow rate iding normally is many times less than the calculated tank flow rate, thus prov an additional conservatism during release.

L Rev. 6 - 9/85 1.0-5 Q_ RAND GULF, UNIT 1 - ~~ _

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