ML19332D719

Rev 2 to Odcm,Incorporating Resin Sampling & Radioactivity Analysis

ML19332D719
Person / Time
Site:	Comanche Peak
Issue date:	11/30/1989
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML19332D716	List: ML19332D715 ML19332D719
References
PROC-891130, TXX-89711, NUDOCS 8912050155
Download: ML19332D719 (15)

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- TABLE-0F CONTENTS .

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.[ TList of > Tables .

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. List of' Figures?

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1. .. Cross Reference to Technical Specifications and_ REC '

viii i References .

4 'xi a ~ Introduction'

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PART 1 - RADIOLOGICAL EFFLUENT CONTROLS

'SECTION 1.0:- DEFINITIONS- I 1  %.

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!SECTION 2'0 - NOT USED'-

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SECTIONS 3.0~AND 4.0 - CONTROLS AND St>RVEILLANCE I 3/4-0

. REQUIREMENTS-3/4.0 - ' Applicability I 3/4-1 >

3/4.3. 3.4 ' Radioactive Liquid Effluent Monitoring > Instrumentation I 3/4-3 x

3/4.3.3'.5 . Radioactive Gaseous Effluent Monitoring Instrumentation I 3/4-8 F '

3/4.3.3.6 ' . Meteorological Monitoring Instrumentation- I 3/4-13. k 3/4.7.15.- Sealed Source Leakage "

.I 3/4-15.

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3/4.~ 11.1.1 7 ' Liv,Jid Effluent Concentration I 3/4-17 i 3/4.11.1.2 - Liquid-Effluent Dose '

I 3/4-21 3/4.11.1.3=- Liquid Radwaste Treatment System I 3/4 22 13/4'.11.1.4 - Evarcrat.1on Pond I 3/4-22a 13/4.11.2.1 - Gaseous Effluent Dose Rate I 3/4-23

3/4.11.2.2'- Gaseous Effluent Dose - Noble Gas I 3/4-27 4

'3/4.11.2.3 - Gaseous Effluent Dose - Iodine-131, a '

Iodine-133, Tritium, and Radioactive I 3/4-28

- Material in Darticulate Form 3/4.11.'2.4 - Gaseous Radwaste Treatment System I 3/4-29 l

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j RADI0 ACTIVE EFFLUENTS

- EVAPORATION POND-p l j

WS CONTROLS Q l 1

3.11".1.4 The qualitity of radioactive material contained in the evaporation

-pond shall be. limited by the following expression:

E'I < 1.0 v jcj

_ exclu' ding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day' half life, kj = ' pond inventory limit for single radionuclide "j" (Curies),

Cj ' - - 10 CFR 20, Appendix B, Table II, Column 2, concentration for

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single radionuclide "j" (microcuries/ml),

V;= de;ign volume of liquid and slurry in the pond (gallons), and

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i 264.= conversion unit (microcuries/ Curie per milliliter / gallon).

IAPPLICABILITY: At all times. i l

ACTION:  !

a.- .With the quantity of radioactive material in the evaporation pond-- 1 h exceeding the above limit, immediately suspend all additions of radioactive material to the pond. 2j

' b.

The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

~SURVEllLANCE RE0VIREMENTS -I

(

4.11.1'.4 The quantity of radioactive material contained in each batch of {

slurry (used powdex resin) to be transferred to the evaporation pond shall be  ;

determined'to be within the above limit by analyzing a representative sample  :

of. the slurry, and batches to be transferred to the evaporation pond shall be  !

limited by: the expression:  !

O J pCl/gm l f < o.000 R Ci/mi where:

concentration of radioactive materials (microcuries/gm) in wet, , ';

! Qj ' =

drained slurry (used powdex resin) for radionuclide "j", excluding i tritium, dissolved or entrained noble gases, and radionuclides '

with less than an 8 day half-life. The analysis sball include at '

least Ce-144, Cs-134, Cs-137, Co-58 and Co-60. Estimates of the  :

Sr-89 and Sr-90 batch concentration shall be included based on the i most recent quarterly composite analysis, t REV. 2 COMANCHE PEAK - UNIT 1 I 3/a-22a 11/89 l

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' 10 CFR 20; Appendix B,. Teble II, Column 2, concentration for. -2 single radionuclide "j" (microcurie:/ milliliter), and .

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1 l bay 0 ACTIVE EFFLUENTS D

BA';ES l

f RQSI (Continued)

P j This. control appliu to the release of radioactive materials in liquid t

L effluents from each unit-at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportional among the units sharing that system. ,

,$/4.11.l.3 LIOUID RADWASTE TREATMENT SYSTEM '

The 0PERABILITY of the Liquid Radwaste Treatment System ensures that this system.will~ be available for use whenever liquid = effluents' require treatment prior-to release to the environment. The requirement that the appropriate H K

= portions of this system be used when specified provides. assurance that the releases of radioactive materials in liquid effluents will be kept "as low as

~is: reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of A;.ptndix A to 10 CFR Part 50 and the

design objective given in Section II.D of Appendix I to 10 CFR Part 50. The ,

specified limits governing the use of appropriate pcrtions of the Liquid  ;

.Radwaste' Treatment System were specified as a suitable fraction of the dose-

~ design objectives-set-'forth in Section II.A of Appendix I,10 CFR Part 50 for liquid effluents. '

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<This control. applies to the release of radioactise materials in liquid Jeffluents from each unit at the site. For units with shared Radwaste Systems, the' liquid ef fluents- from.the shared system are to be proportioned among the

• funits sharing that system.

2L4dl.1.4 EVAPORATION POND 4 The inventory limits of the evaporation pond (EP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in Control 3.11.1.4 assumes the pond inventory is uniformly mixed, that .ne pond is located in an unrestricted area as defined in 10 CFR Part 20 l

and that the. concentration lhtt in Note 1 to Appendix B of 10 CFR Part 20 applies.

2 The batch limits of slurry to the EP assure that radioactive material in L'

E the slurry transferred to the EP are "as low as is reasonably achievable" in  :

accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of slurry will be-transferred to the EP unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation

-is less than the ratio of the 10 CFR Part 50, Appendix I, Sec+1on II. A. total body level to the 10 CFR 20.105(a), whole body dose limitatior., or that:

I j C l 3Soo5***

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? # ,  : RADI0ActlVEEFFLUENTSL i- .

- SA.511. -

' EVAPORATION PONDi(Continued) ,

where:

cj = radioactive slurry concentration for radinnuclide "j" entering the

, UNRESTRICTED AREA EP, in microCuries/ milliliter, and Cj = 10 CFR 20, Appenoix B, Table II, Column 2, concentration for

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single radionuclide_ "j", in microcuries/ milliliter.

- The average' concentration of radioactive ~ materials in a particular batch 4

- of resin slurry released to the EP is ' dependent upon the slurry volume to

- ~ resin weight ratio. Additionally,-the wet drained slurry density is

' approximately-l'gm/mi ant the absorption characteristics for gamma radiation are essentially that of water. Therefore,

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The batch. limits provide assurance that activity input to the EP will be

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i minimized, and- a means of identifying that the radioactive material released t

.is within_the inventory limitation of Control 3.11.1.4.

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COMANCHE PEAK - UNIT 1 I B 3/4-5 /[39 x

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• / l3/4.1I.f-GASEOUSEFFLUENTS 3/4;11.2.1 DOSE RATE

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This. control it provided to ensur3 that the dose at any time at and beyond'the SITE BOUNDARY-from yeseous effluents from all units on the site -

fn' .will be:within the annual dose 11mits of 10CFR20 to UNRESTRICTED AREAS. The- .

annual dose limits are the doses' associated with the concentrations of 10CFR20s Appendix B. Table ~I, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not

. result.in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, 1 either withinoor outside the SITE B0UNDARY, to annual average concentrations W , _

exceeding the limits specified.in Table II of 10CFR20- Appendix B (10CFR L 20.106(b)). .For; MEMBERS OF THE PUBLIC.who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE-PUBLIC will usually be sufficientlyslow to compensate.for any increase in the e.tmospheric diffusion c f6ctorfaboveLthat'for.the SITE B0UNDARY. The methodology for calculating doses for such MEMBERS OF'ThE PUBLIC shall be given in the ODCM.

-The specified frelease rate limits .restiict, at all times, tne corresponding igamma and betaLdose rates above background to a MEMBER OF THE~PUBLIC at or

.beyond<the SITE BOUNDARY to les;'than or equal to 500'mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits.also restrict, at aid times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to'1500 mrems/ year, i

This control applies' to the release of radioactive materials in gaseous effluents from all units at the site.

The relaired detection capabilities for radioactive materials in liquid waste sample-s are tabulated in terms of the icwer limits of. detection (LL9s).

-Detailed discussion ~of-the LLDs and other detection limits can be found in Currie, L. A., " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Heasurements."

HUREG/CR-4007 (September 1984), and in the HASL Procedures Hanual, HASL-300.

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4 BAAI0 AC71VE iEFFLUENTji -

1 LASES _

3/4.11.2.2 00SE -' NOB'LE GASES

~ -This control- is provided to implement the requirements of Sections II.B.

III.A and IV.A of 10CFR50,-Appendix 1. The control implements the guides s-t-forth in-Section I.B:cf Appendix 1. The ACTION statements provide the required operating flexibility and at the sale time implement the guides set-forth in'Section IV;A of Appendix I to a> a'9 that the releases of radioactive material,in gaseous effluents to UNRESTRICTEh AREAS will be kept- -

j, "asElow as is reasonably. achievable." The Surveillance Requirements implement the raquirenients in Section III. A of Appendix;I that conformance with the-

-guides of Appendix I be shown by calculational procedures based on models ano data such that-the actuel exposu.e of a HEMBEP. OF THE PUBLIC through

~

, appropriate pathways is unlikely to be suostantially underestimated. The dose calcuiation'methodologyfand parameters established in the ODCH for-calculating

'the' doses due to'the actual 7 release rates of the radioactive noble gases in-gaseous Leffluentsf are consistent with the methodology provided in Regulatory Guide- 1.109.." Calculation of Annual Dose to Han from Rcutine Releases of

' Reactor Eff-luents for ths Purpose of< Evaluating Compliance with .10CFR50,

' Appendix i l," Revision 1, October 1977 and Regulatory Guide 1.111. "Hethods for Estimating Atmospheric. Transport and Dispersion of Gaseour Ef'luents in Routine- Aeleases from Lignt-Water Cooled Reactors, Revision- 1. July 1977.

=The'0DCH-equations provided for determining the air doses at and beyond the

SITE B0UNDARY are based upon the historical averaga atmospheric conditions.

This control applies to: the release of radioactive materials in gaseous  ;

effluents from each unit at.the site. For units with shared radwaste y treatment systems, the gaseous effluents from the shared systeN<are a proportioned among the units sharing'that system.

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RADIOACTIVE EFFLUENTS.

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" '1L4 11.2.L -DOSE - 10 DINE-131. 10 DINE-133. TRITIUM. AND RADI0ACTIVF,_ MATERIAL .

IN PARTICULATE = FORM- I s

This control is provided to implement the requireuents of Sections II.C.

, III.A and~IV.A of 10CFR50, Appendix 1. The Controls are the' guides set forth

.itLSection~II.C of Appendix I. The ACTION statements provide the required i operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the. releases of radioactive  ;

materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably. achievable," The'0DCH calculatienal methods specified in the.

~

Surveillance Requirements implernent the requ:rements in Section III. A of-Appendix I: thai,conformance with the guides of Appendix I be'shown by calculational procedures based on models and data-such that the actual exposure of a HEHBER OF THE PUBLIC through appropriate pathways is unlikely to

'be substantially underestimated. The 00cM calculational methodology and  ;

parametecs for calculating tF.e doses due to the actual release rates of the subject materials are. consistent with the methodology provided in Regulatory Guide.l.109,'" Calculation of Annual Doses to Man from Routine Releases of

' Reactor Effluents for the Purpcse of Evaluating Compliance with.10CFR50, Appendix I," Revision 1. October 1977 and Regulatory Guide-1.111. " Methods for Estimating Atmospheric. Transport and Dispersion of Gaseous Effluents in s Routine Releases from Light-Water-Cooled Ra, tors," Revision 1, July 1977.

Th;se: equations also provide for determining ne actual doses based upon the historical average atmospheric conditicas. The release rate specification for

' Iodine 131, looine-133,-tritium. and radionuclides in particulate form with half-lives. greater than 8 days is dependent upon the existing radionuclide

pathways,to man'in the-areas at and beyond the SITE BOUNDARY. The pathways

-that were examined in the development of the csiculations were: (1) indivi' dual inhalation of airborne radionucludes, (2) deposition of radionuclides.onto green leafy vegetation with subsequent consumption by man, L

(3) deposition.onto grassy areas where milk animals and meat-producing aniinals-F

' graze with consumption of the milk and meat by man, and (4) deposition on the ground:with subsequent exposure of man.

-This control applies to the release of radicactive materials in gaseous effluents from each urdt at the site. For units with shared radweste treatment systems, the gaseous effluents from the shared system are

• proportioned among tne units sharing' that system.

s REV. O COMANCHE PEAK - UNIT 1 I B 3/4-8 3/89 r

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' RADIOACTIVE EF F LUENTS

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., 3/4.11.2.4 GASEOUS RADW/STE TREATMENT SYSTEH Th; :PERABILIT)-of the WASTE GAS HOLDUP SYSTEM and the PRIMARY PLANT

. SYSTEh ensures that-the systems will be available for use whenever- gaseons Eef fluents requi*,*e~ treatment prior to release to the environment. The requirement that the appropriate protions of these systems be used, when.

16 specified, provides reasonable assarance that the releaser of radioactive materials in gaseous effluents will be kept "as low as is reasonably '

achievable." This control implements the requi.uments of 10 CFR 50.36a, l General Design Criterion 60 of Appendix A~ to 10 CFR Part'50 and the design -

,As objectives given in Section II.D of Appendix I to 10 CFR Part 50. The

.specified limits governing the use of- appecpriate portions of the systems were specified as o suitable ~ fraction of the dose design objectives set forth in Sections !!.B and :lI~.C' of Appendix I,10 CFR Part 50, for gaseous effluents. ,

This control applins to the release of radioactive materials in gaseous g, effluents from each unit at the site. For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are

, proportioned among the units sharir.g that system. -

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,I AtIAhhment 1foiTXX-89711

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E RADIDACTIVE EFFLU[ fili-p; BASES' q; ~ -f

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3/4.11.4 T07%RQS1 This control is provided to reset the dose limitations of 40 CFR Part 190 that hdve been incorporated into 10 CFR Part 20 by 46 FR 18525. The control requires thel preparation and submittal of. a Special Report whenever the

' calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal' to 75 mrems.

For sites containing up- to four reactors, it is highly unlikely that the

>' , resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design i objectives- of Appendix I, t.nd if direct radiation doses f rom the units

'(including outside ~ storage- tanks, etc.) are kept small . The Special Report will describe a course of action that should result in the limitation of the annual dose to a HEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

For the-purposes of-the Special Report, it may be assumed that the dose commitment to the NEMBER OF THE PUBLIC from other uranium fuel cycle sources ..

is negligible, with'the exception that dose contributions from other nuclear I fuel cycle facilities at the same site or within a radious of 0 km must be -l considered. If the dose to any NEMBER OF THE PUBLIC is edimated to exceed 4 the requirements of '40 CFR Part 190 the Special Report with a request for a

' variance (provided the release conditions resulting in-violation o+ 40 CFR Part 190 have not already been corrected), in accordance with the provisions of. 40 CFR:190.11 and 10 CFR 20.405(c) - is considered to be a timely request )

and fulfills the requirements of 40 CFR Part 190 until NRC staff- action is i

. completed. The variance only relates to the -limits of 40 CFR Part 190, and does not apply in'any way to the other requirements for dose limitation of 10 j CFR Part 20,- as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is

~

I not: considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. ,

I REV. 0 COMANCHE PEAK - UNIT 1 1 B 3/4-1n 3/89 1

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l r 6 2 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING b

. BASES-r J

7 3/4.12.1 MONITORING PROGRAM m

The Radiological Environmental Monitoring Program required by this I control provides representative measuremet.ts of. radiation and of. racio ,ctive y materials-in those exposure pathweys and'for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting

, -from the plant cperation. 'This monitoring program implementsSection IV.B.2.  !

W of Appendix 1 to 10 CFR Part 50 and thereby supplements the Radiological

~

Effluent Monitoring Program by verifying that the measureable concentrations a of-radioactive materials and levels of radiation are not higher than expected

~ on the_ basis of the effluent measurements and the modeling of_the

. environmental exposure pathways. Guidance for this monitoring program is provided bycthe Radiological Assessment Branch Technical Position on

. Environmental'Honitoring, Revision 1. November 1979. The initially specified monitoring; program will be effective for at least the first 3 years of  ;

y = commerci al - operati on'. Following this-period, program changes may be initiated based on operational experience.

3.

cThe required detection capabilities for environmental sample analyses are *

. tabulated in terms of the lower limits of detection. (LL0s), The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined.

Ms.an:g priori-(before the fact) limit representing the capability of a measutement. system and not as an a posteriori (after the fact) limit for a

.particular measurement Detailed discussion of the LLD, and other detection limits, can be fand in Currie L. A.. " Lower Limit of Detection: Definition and Elaboration of a

-Proposed' Position for Radiological Effluent and Environmental Measurements " ,

-NUREG/CR.4007 (September.1984), and in the HASL Procedures-Manual HASL-30Q, 3/4712.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at

. and beyond the SITE BOUNDARY are. identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of.this census. The best information from the docr-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section

• IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of

. greater than'50 m2 provides assurance that sig11ticant exposure pathways via

-leafy vegetables will be identified and monitored since a garden of this size

-is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was u:ed for growing broad leaf vegetation (i.e., similar to

. lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 REV 0 COMANCHE PEAK - UNIT 1 I B 3/4-11 3/89 l

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< / Att'achment I to TXX-80711 -

. Page 13.of'13?

' RADIOLOGICAL' ENVIRONMENTAL MONITOR 1N,Q-(9;, '

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11/4'.1 2 . 3 INTERLABORATCRV COMPARISON' PROGRAM

-The- requirement for participation 'in an approved Interlaboratory Co.?parison Program is provided to ensure that independent checks on the precision and' accuracy-of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance <

program for envirornental monitoring in order to demonstrate that the results

-are valid for'the purposes _of Section IV.B.2 of Appendix I-to 10 CFR'Part 50.

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p 1 COMANCHE PEAK, STEAM ELECTRIC STATION OFFSITE DOSE ~ CALCULATION MANUAL 1 INSTR'JCTION SHEET J The following instructional information is being furnished to help' insert Revision 2 irito the. Comanche Peak Steam Electric Station ODCM.

Op Discard the old sheets and inser the new sheets, as listed below. Where a new

-sheet is- to be inserted 'and it~ does not replace an existing page, it should be inserted sequentially according to its designated page number.

Holders of the CPSES ODCM should keep these instruction sheets in tiier front of

e. the Effective,Page Listing as a record of the changes, until a new listing is

i ssued; Remove Insert Part I i- i

'I 3/4-22a  :

thru l I 3/4-22b l i

I B 3/4 4 I B 3/4-4 thru thru j

' I B 3/4 LI B 3/4-12 i s

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- ,DETAll.ED' DESCRIPTION Page 1. ,

a. ,

x0DCM, Page- .

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(as' amended). GrouD ~ Descr1Dti on 9 1 N (41l 4 - 4 :This page of the Table of Contents is revised to add an entry for the controls; and Surveillance Requirements  ;

h for the Evaporation Pond.

!!E Editorial: '

(his change is made to accomodate the addition'of the sampling and radioactivity analysis requirements for F

resins.

ODCM Change Request Number:' 00-89-2.1 Related SER Section:.11.2.1.2 L SER/SSER Impect: No p

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I 3/4-22a 3- _See Page No(s):I B 3/4-4_& 5

%, " Adds'the Control and Surveillance Requirements for the' >

-Evaporation Pond, c, c -Addition: '

This change is made to incorporate the resin sampling and radioactivity analysis requirements (as identified s -

in SER section:11.2.1.2) in the ODCH,.and to correct' the response provided in item 7 of TXX-88777'(dated December 16, 1988) which indicated that these require-ments were specified in the CPSES Radiuactive Effluent and Environmental Monitoring Manual _(REEMM).

0DCM Change Request Number: OD 89-2.2 Related SER Section:-11.2.1.2 SFR/SSER Impact: Yes Section 11.2.1.2 of the SER should be revised to 1 reflect the fact that the resin sampling and radio-J activity analysis requirements have been incorporated in the ODCH.

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