ML20066A814

Rev 5 to Odcm

ML20066A814
Person / Time
Site:	Comanche Peak
Issue date:	12/21/1990
From:	Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
References
PROC-901221, NUDOCS 9101040128
Download: ML20066A814 (18)

Text

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OFFICE MEMORANDUM CPSES 9029494 TUS 90481 i December 21, 1990 l J

Ho Response Required TO: All Copy Holders COMANCHE PEAK STEAM ELECTRIC STATION REVISION 5 TO THE CPSES OFFSITE DOSE i CALCULATION MANUAL (00CM) l l

Enclosed is Revision 5 to the CPSES Offsite Oose Calculation Manual (00CM) and receipt acknowledgement sheet, Please page check your assigned copy of the j ODCM against the updated Effective Page Listing (EPL) which is included with

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Revision S. Return the acknowledgement sheet as specified. l

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If you have any questions regarding the ODCM, contact Greg Bell at (214) 812 8219.

F e6d D. R. Woodlan Docket Licensing Manager GLB/grp Enclosure c- CCS E06

! File # 953 I

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9101040128 901221

{DR ADOCK 05000445 PDR

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COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL

, INSTRUCTION SHEET i

The following instructional information is being furnished to help insert Revision 5 into the Comanche Peak Steam Electric Station ODCM. In accordance

! with CPSES Technical Specification 6.14b, ODCM Revision 5 became effective-i when it was approved by the Vice President, Nuclear Operations on December 20, 1990, i

Discard the old sheets and insert the new sheets-as -indicated below.

Holders of the CPSES ODCM should keep these instruction sheets in the front of the Effective Page Listing as a record of the changes, until a.new listing is issued.

Remove In11tt

-vi vi xi xi 11 1-15 (Table 1.1) II l 15 (Table 1.1)

II 2 18 11 2 18 II 2 19  !! 2-19 Oi II 2-45 (Table 2.4) II 2-45 (Table 2.4 Sheet 1)

II 2-46 (Table 2.5) II 2-46 (Table 2.4 Sheet 2)

G3 G-3 EPL-1 through EPL 8 EPL-1 through EPL 8 5

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. - List of Tables Table No, li.tig h21 2.4 Controlling Receptor Pathways and II 2 45 5 Locations, and Atmospheric Dispersion Parameters (For Dose Calculations Required by Radiological Effluent I Control 3/4.11.2.3) 2.5 Deleted II 2 46 5 3.1 Environmental Sampling Locations II 3 3 O '

l 12/90

REFERENCES

1. B9914. J.S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield, Od 4raparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG 0133 (October 1978),

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effli.ents for the Purpose of Evaluating Compliance with 10CFR Part S0.

Appendix 1, U. S. NRC Regulatory Guide 1.109. Rev.1 (October 1977).

3. " Environmental Report," TV Electric, Comanche Peak Steam Electric Station.

4. " Final Safety Analysis Report," TV Electric, Comanche Peak Steam Electric Station.

S. Methods for Estimating Atmospheric Transport and Of;persion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).

6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light Water Cooled Reactors, U.S.

NRC Regulatory Guide 1.111, Rey, 1 (July 1977).

7. Meteorology and Atomic Energy; Edited by Slade, O. H.; U. S. Department of Commerce (July 1968).

5

8. " Unit 1 Technical Specifications," TV Electric, Comanche Peak Steam Electric Station.

9. Implementation of Programmatic Controls for Radiological Effluent 3 Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS i to the Offsite Oose Calculation Manual or to the Process Control Program (Generic Letter 89 01), USNRC, January'31, 1989.

10. CPSES Technical Evaluation No. RP-90 3077, " Calculation of Site Related 5 Ingestion Oose Commitment Factors For Sb 122."

11. " Calculation of Annual Doses to Man from Routine Releases of Reactor 5 Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," USNRC Regulatory Guide 1.109 (March 1976).

l LO 12/90

. . _ . , _ - - _ m TABLE 1.1 O SITE RELATED INGESTION DOSE COMMITMENT FACTOR Aj, (mrem /hr per uC1/ml)

LyfG GI LLI ISOTODE SE Lly.iB T BODY THYROID KIDNEY Pr 144 4.31E 03 1.79E 03 2.19E 04 0.00E+00 1.01E 03 0.00E+00 6.19E 10 Nd 147 9.00E 01 1.04E+00 6.22E 02 0.00E+00 6.08E 01 0.00Er') 4.99E+03 W 187 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E400 8.34E+04 Np 239 1.28E 01 1.25E 02 6.91E 03 0.00E+00 3.91E 02 0.00E+00 2.57E+03 j

• Sb 122 1.98E+01 3.90E 01 5.79E+00 2.69E 01 0.00E+00 1.03E+01 5.68E+03 5

• • Sb.124 2.41E+02 4.54E+00 9.50E+01 5.81E-01 0.00E+00 1.87E+02 6.81E+03

• The adult dose conversion factors, DFj, for Sb 122 are not published in 5  !

Reference 2. The calculation of dose conversion factors and site related ingestion dose commitment factors for Sb 122'is documented in Reference 10.

• • The adult dose conversion factors, DFj, for Sb 124 are not published in 5 j Reference 2. The site related dose commitment factors for Sb 124 were calculated using the " Adult Ingestion Dose Factors

• given in Table A 3=of Reference 11, and Equation 1-10 of Part II, Section 1.2.1 of this Manual.

i Il 1 15 Rev. s l 12/90 l

= .. . .

-. - __~ -. - . . _ - - __ - - -. . .- -- .-. ..

Note: If the methodology in this section is used in determining dose to an individual ~ rather than air dose O due to noble gases, substitute Ki for M i , (Li+

i 1.1 Mj) for Nj, and the Annual Average X/Q values from Table 2.4 for the highest annual average relative 5 concentration (X/Q) at the SITE BOUNDARO

$ 2.2.2 Dose Due to Radiciodines. Tritium. and Particulates For implementation of Radiological Effluent Control 3/4.11.2.3,-

the cumulative dose to each organ of an individual due-to iodine 131, iodine 133, tritium, and particulates with half-I lives greater than 8 days will be calculated at least once per 31 days and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year.

The dose over the desired period will be calculated as follows:

Op = dose due to all real pathways to organ, o, of an -  !

individual in age group, a, from iodine-131, iodine 133, tritium, and radionuclides in particulate.

j O- form with half-lives greater than eight days (mrem).= l Op = PATHS 3.17 x 10 8 W' IP{TR$,a,oiQ'i aq. 2-n)

Where: W' the dispersion parameter for estimating the dose j to an individual at the locetion where the combination J of existing pathways and recepter age groups indicates the maximum potential exposures. Locations of interest 5 -i t

are listed in Table 2.4, W' = X/Q for the inhalation pathway in sec/m3 X/Q is the annual average relative concentration at the location of interest. Values for X/Q are listed in  ;

Table 2.4. If. desired, the highest individual receptor X/Q valve may be used, or

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L q W' = D/Q for the' food and ground plane pathways in m 2, 0/Q is the annual average deposition at the location 5 of interest. Values for 0/y are listed in Table 2.4.

If desired, the highest individual receptor D/Q value may be used.

NOTE: For tritium, the dispersion parameter, W'.is taken as the annual average X/Q vclues from Table 2.4 for '

inhalation, food and ground plane pathways.  ;

RPi .a.o = dose factor for radionuclide i. pathway p, age group a and organ o, in mrem /yr per uC)/m3 fer the inhalation pathway and m2(mrem /yr) per uCi/Sec.for food and-ground plant. pathwtys, except for tritium'which is in mrem /yr per uti/m3 for all pathways. The values for RPi ,a,o for each pathway, radionuclide,-age group and organ are listed in Table-2.3*.

Q'i = cumulative release of radionuclide, i, during the period of i'it? rest (uCl). Q'j is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required F; Radiological Ef *'uent Control 3/4.11.2.1.

Table 4.11-2. _[

!&PT = lodines, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed.

PATHS = the real pathways of exposure to' individuals at the locations of interest as indicated in Table 2.4. 5

• • the methodologies used for determining values of RPi ,a o for each pathway are given in Appendices B through F.

11 2 19 .Rev. 5 12/90 ,

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. a TABLE 2.4 l (Sheet 1 of_2)

CONTROLLING RECEPTOR PATHWAYS"AND LOCATIONS (NOTE 1),1AND O ATMOSPHERIC.0ISPERSION PARAMETERS (FOR DOSE CALCVLATIONS REQVIRED BY RADIOLOGICAL EFFLUENT CONTROL- 3/4.11.2.3)

Pathway 01 stance X/Q- 0/Q Sector (Note 2) IMiles)- (Notes 3. 4) (Notes 5. 6)

Resident 2.20 9.28E 07 5.32E-09 N Garden None -- --

Milk Cow None -- -

Resident 2.30 5.12E-07 2.60E 09 NNE Garden 2.40 --- 2.30E 09 .,

Milk Cow None. -- --

Resident 2.30 3.58E 07 1.28E 09 NE Garden 2.70 --

8.92E-10 Milk Cow 4.50 -

2.70E-10 Resident 2.40 2.58E 07 7.08E-10 ENE Garden 2.60 ---

5.77E-10 5 Milk Cow .None- -- --

Resident 2.40 3.02E-07 6.62E-10 E Garden None -- -

Milk Cow None -- --

Resident 2.30 3.68E-07 9.00E-10 l ESE Garden 2.30 --

9.00E-10 Milk Cow None --- --

1 Resident 2.00 7.10E-07. 2.80E-09 SE Garden 2.50 --

1.60E-09 Milk Cow None -- --

t Resident 1.60 9.96E-07 5.92E-09 SSE Garden 4.80 --

4.48E-10' Milk Cow 2.20 --

1.80E 09 Resident 1.60 7.74E-07 '

4.66E-09 t S Garden 4.30 --

4.34E-10 l' ilk Cow 4.20 --

4.56E-10 w/ f,esident 1.90 4.42E-07 2.06E-09 SSW Garden None -- --

Milk Cow None- -- --

Rev. 5 II 2-45 12/90 l

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.. . q TABLE 2 4.

(Sheet 2)

CONTROLLING RECEPTOR PATHWAYS- AND-LOCATIONS (NOTE 1). AND-( ATMOSPHERIC DISPERSION PARAMETERS (FOR. DOSE CALCULATIONS-  :

REQUIRED BY. RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) j 1

Pathway Distance X/Q .

0/Q Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6) l

[ Resident 1.00 1.60E 06 7.50E 09 1

l SW Garden 2.10 --

1.10E Milk Cow ~ 4.70 --

~1.79E-10

-Resident 1.00- -1.80E-06 .6.50E-09~

WSW Garden ' l .10 - --

5.64E 09 Milk Cow None -- --

Resident 1.50 -8.40E-07 -2.80E 09 W Garden 1.50 --

2.80E-09 Milk Cow None -- -- '

Resident 2.00 7.30E l2.50E-09 WNW Garden 3.00 -

1 04E 5 ,

Milk Cow None. -- --  !

O Resident' 2.70 6.98E-07 2.24E-09 Garden NW None- -- --

Milk Cow None -- --

Resident 2.70 7.62E-07~ '3.22E-09 .

Garden 4.90-NNW --

8.48E-10~

Milk. Cow 4.50 -- .

9.60E-10 3

NOTES: T (1) Receptor locations are taken from the nearest receptor locations identified in the CPSES 1990 land use census.

(2) In addition to the pathways 'shown, the inhalation and ground plane pathways are present_at the nearest resident.-

(3) The units for X/Q.are Sec/ Cubic Meter.

(4) X/Q Values at distances 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, and 6.0 miles-were taken from Table 2.3-16 " Average Annual Relative Concentration at .

CPSES," of the CPSES Environment Report, Operating Licensing Stage (Reference 3). The X/Q values -at.other distances .were-determined by-linear . interpolation.

(5) The units for 0/Q are inverse square meters (6) D/Q values at distances 1.0,1.5, 2.0, 2.5, 3.5, 4.0, 4.5, and 6.0 miles p - were taken from Table 2.317, " Average Annual Relative Deposition Rate,"

V of the CPSES Environmental Report, Operating License Stage (Reference 3).

The 0/Q values at other distances were determined by linear interpolation; II 2-46 Rev. 5 12/90

E -

4 SUPPLEMENTAL GUIDANCE STATEMENT #3

SUBJECT:

TRITIUM LEAKAGE FROM THE TURBINE GENERATOR PRIMARf WATER COOLING SYSTEM (TGPWCS)

The purpose of this statement is to provide guidance for handling tritium 5 detected in the Turbine Building sumps or Waste Water Holdup Tanks (WWHTs),

due to leakage from the TGPWCS, when there is no primary-to-secondary _ leakage.

(Note: Tritium is used in the TGPWCS as a tracer to detect leakage of-cooling water into the generator coils.) Discharge of the Turbine Building Sumps or WWHTs to the Low Volume Retention Pond may continue when tritium is detected due to known leakage from the TGPWCS, provided that: (1) the average tritium concentration does not exceed the 10 CFR 20 limit for release to an unrestricted area (3x10-3 pCi/ml); and (2)_ there are no' detectable principal gamma emitters or 1-131. Per 10-CFR 20.106(a),_ concentrations may.be averaged over a period of not greater than 1 year.

Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, requires that Turbine-Building Sump discharges be diverted to the Waste Water Holdup. Tanks when radioactivity is present in the sumps at concentrations greater than or-equal to the maximum LLD values given in Table 4.11-1. It also requires that .the 5 Waste Water Holdup Tanks be discharged directly to the Circulating Water Discharge Tunnel when -the maximum LLD valves are exceeded. For tritium, the value established for required diversion and discharged to -the Circulating-Water Discharge Tunnel is -lx10-5 -uCi/ml. These requirements are established based on acceptable activities in the sump resulting from primary-to-secondary leakage. This supplemental guidance, which allows discharges of 5 tritium to continue to the Low Volume Retention Pond provided _that the average tritium concentration does not exceed 3x10-3 pei/ml, is acceptable since the total activity of tritium is a known, fixed quantity. (Note: The maximum inventory of tritium in the TGPWCS is approximately 700 mci.) Additionally, the dose associated with the release of tritium, due to TGPWCS leakage, .is.

negligible, as denionstrated by the calculation shown below.

The total activity of tritium discharged due to TGPWCS leakage shall be determined from sampling of the TGPWCS and reported in the Semiannual O

V Radioactive Effluent Release report.

G3 Rev. 5 12/90 1

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l CPSES - 00CM-List of Effective Pages-r -- Pre f ace -

The Effective Page Listing (EPL)~.provides a tabulationiof the current- j' pages in the CPSFS 00CM.

Each page in the CPSES-0DCM is. identified with a page_ number,-

including pages that contain tables or figures,- j o

A revision number and date are included on each page. The: revision number and date are changed when the change represents a_ substantive- -!

revision to the information that-is provided on the page. If the page-is revised or reprinted but the revision is not considered substantive '

(i.e., it is an editorial correction), the revision number will:not be changed, but'will have the reprint date, Since the EPL may not-be updated with each revision, an Instruction Sheet (s) will be provided for_ subsequent revisions of the CPSES ODCM; it should be retained immediately in front-of the EPL : To identify the effective revision level of a page in the CPSES ODCM, check these Instruction Sheets first and, if not found, the EPL-second, if any effective page cannot be-found, notify TV Electric- Nuclear Licensing and the required effective pages wil1 be provided. Contact.

may be made by phone (214/812 8873) or by mail. A marked up copy of-pages from the Instruction sheets or the EPL_-is_a convenient way..to O identify the required pages.

EPL-1 December 1990

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