ML20210S821

Forwards Sser Re App I Conformance.Radwaste Sys Capable of Achieving ALARA

ML20210S821
Person / Time
Site:	Satsop
Issue date:	04/09/1976
From:	Vollmer R Office of Nuclear Reactor Regulation
To:	Deyoung R Office of Nuclear Reactor Regulation
References
CON-WNP-1641 NUDOCS 8605290427
Download: ML20210S821 (15)

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APR 0 91976 SUPPLEMENT TO SAFETY EVALUATION REPORT FOR WASHINGTON NUCLEAR PROJECT, UNITS 3 4 5 REGARDING COMPLIANCE WITH APPENDIX I 0F 10 CFR PART 50 11.0 Radioactive Waste Management On April 30, 1975, the Nuclear Regulatory Commission adopted Appendix I to 10 CFR Part 50, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Reasonably Achievable for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents'".

To effectively implement the requirements of Appendix I, the NRC staff has reassessed the parameters and mathematical models used in calculating releases of radioactive materials in liquid and gaseous effluents in order to comply with the Commission's guidance.

This guidance directed that current operating data, applicable to proposed radwaste treatment and effluent control systems for a facility, be considered in the assessment of the input parameters.

The staff has completed its reassessment and these parameters, models and their bases are given in Regulatory Guide 1.BB, "Calcula-tion of Releases of Radioactive Materials in Liquid and Gaseous Effluents from Pressurized Water Reactors (PWRs)," September 9, 1975.

By letter of September 12, 1975, the applicant was requested to submit additional information concerning the means proposed to be employed to keep levels of radioactive materials in effluents from the Washington Nuclear Project, Units 3 and 5, to unrestricted

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.. I' 11.0 areas "as low as reasonably achievable" in accordance with Appendix I guidelines. In a letter to' the Commis:: ion, dated October 24, 1975, Washington Public Power Supply System chose 4 -

to perform the cost-benefit analysis required by Section II.D of-Appendix I to 10 CFR Part '50.

W have performed an independent evaluation of the applicant's proposed methods to meet the requirements of Appendix 'I.

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evaluation consisted of:

(1) a review of the information provided by the applicant in response to the letter of September 12, 1975; (2) a review of the applicant's proposed radwaste treatment and effluent control systems as described in the PSAR, as amended through Amendment 27 (December 1975) and in the ER, as amended through Amendment 5 (November 1975) and through ER Supplement 6 (October 1975); (3) the calculation of new source terms based on models and parameters as given in Regulatory Guide 1.BB (September 1975); and (4) the calculation of the cost-benefit of potential radwaste treatment augments, using doses based on the source terms calculated in ($)' above and guidance as given in Regulatory Guide 1.110,3 Cost-Benefit Analysis for Radwaste Systems for Light-Water Cooled Nuclear Power Reactors" (March 1976).

The individual and population doses were calculated using the guidance in Regulatory Guide 1.109, " Calculation of Annual Average Doses to i

Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I (March 1976).

11.0 Meteorologic and hydrologic factors in the dose calculations were determined using the guidance in Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseou; Effluents from Routine Releases from Light-Water-Cooled Reactors" (March 1976), and in Regulatory Guide 1.EE, " Analytical Models for Estimating Radioisotope Concentration in Different Water Bodies" (September 1975).

We have determined the quantities of radioactive materials that will be released in the liquid and gaseous effluent streams during normal operation including anticipated operational occurrences.

The principal radionuclides expected to be released in liquid and gaseous effluents are given in Appendixes 1.and 2 to this supple-ment. In making these determinations, we have considered waste flows, radionuclide activities, and equipment decontamination factors, which are consistent with those expected over the 30 year operating life of the plant, considering normal operation including anticipated operational occurrences. A list of the parameters used in these determinations is given in Appendix 3.

In our evaluation, we considered releases of radioactive materials in liquid and gaseous effluents for normal opera-tion including anticipated operational occurrences based on expected radwaste inputs over the 30 year operating life of the plant and have determined that for each reactor on the Washing-ton Nuclear Project, Units 3 and 5, site, 1) the release s

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11.0 of all radioactive materials above background in liquid effluents will not result in an annual dose or dose commitment to any individual in an unrestricted area from all pathways of exposure i

in excess of 3 millirems to the total body and 10 millirems to any organ, 2) the release of all radioactive materials above background in gaseous effluents will not result in an estimated annual air dose at any location near ground level which could be occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radiation or 20 millirads for beta radiation, and 3) the release of all radioactive iodine and radioactive material in particulate form above background will not result in an annual dose or dose commitment to any individual in an unre-stricted area from all pathways of exposure in excess of 15 millirems to any organ.

We have also considered the potential effectiveness of augmenting the proposed liquid and gaseous radwaste treatment systems using items of reasonably demonstrated technology and have determined that additional augmentation will not effect reductions in the cumu-lative population dose reasonably expected within a 50 mile radius of the reactor at a cost of less than $1,000 per total body nan-rem or $1,000 per man-thyroid-rem.

We evaluated potential radwaste system augments based on a study of the applicant's systems designs, on the dose information provided in Tables 1 and 2 of this supplement, on the basis of an interim

I 11.0 value of $1,000 per total body man-rem and $1,000 per man-thyroid-rem for reductions in dose by the application of augments, and on the cost of potential radwaste system augments as presented in Regulatory Guide 1.110, March"1976.

l The doses from gaseous releases to the population within a 50 mile radius of each reactor, when multiplied by $1,000 per total body man-rem or $1,000 per man-thyroid-rem, resulted in cost-assessment values of $7,000 to the total body man-rem dose and $8,000 to the man-thyroid-rem dose. Similarly, the doses from liquid releases resulted in cost-assessment values of

$610 to the total body man-rem dose and $1,100 to the man-thyroid-rem dose.

Potential radwaste system augments were selected from the list given in Regulatory Guide 1.110. We considered 10 augments to the gaseous radwaste system and 10 augments to the liquid radwaste system. The Total Annualized Cost,(TAC) for the gaseous radwaste system augments ranged from $8,000 to $660,000 per year. The TAC for the liquid radwaste system augments ranged from $11,000 to

$200,000 per year.

For the 20 augments evaluated, we found that the TAC for each augment exceeded the $1,000 per total body man-rem or $1,000 per man-thyroid-rem cost-benefit ratio. We concluded, therefore, that there were no cost-effective augments to reduce the cumulative population dose at a favorable cost-benefit ratio.

. -I 11.0 Based on our evaluation, we conclude that the liquid and gaseous radwaste treatment systems are capable of reducing releases of radioactive materials in liquid and gaseous effluents to "as low as reasonably achievable" levels in conformance with 10 CFR Part 50.34a and which meet the requirements of Appendix I to 10 CFR Part 50 and therefore are acceptable.

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7 TABLE 1 Comparison of Calculated Doses from WNP Units 3 6 5 Operation With Sect. ions II. A, II.B and II.C of Appendix I to 10 CFR Part 50 (Doses to Maximum Individual per Reactor Unit)

Appendix I Dose Calculated Criterion Design Objective Doses Liquid Effluents Dose to total body from all pathways 3 mrem /yr 2.1 mrem /yr Dose to any organ from all pathways 10 mrem /yr 2.6 'arem/yr

' Noble Gas Effluents

~ Gamma dose in air 10 mrad /yr 2.6 mrad /yr Beta dose in air 20 mrad /yr 4.7 mrad /yr Dose to total body of an individual 5 mrem /yr 0.9 mrad /yr Dose to skin of an individual 15 mrem /yr 2.1 mrem /yr Radioiodines and Particulates" Dose to any organ from all pathways 15 mrem /yr 3.0 mrem /yr

" Carbon-14 and tritium have been added to this category.

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- TABLE 2 Calculated Population Doses (Man-Rem) for Cost-Benefit Analysis,'Section II.D of Appendix I to 10 CFR Part 50*

Pathway Total Body 1hyroid Liquid 0.61 1.1 Gaseous 6.8 8.0

• Based on the population reasonably expected to be within a 50 mile radius of the reactor.

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Principal Parameters Used in the Cost-Benefit Analysis Labor Cost Correction Factor, FPC Region 7" 1.3

,l Indirect Cost Factor" 1.62 b

Cost of Money 7g Capitol Recovery Factor" 0.0806

• From Regulatory Guide 1.110, Cost-Benefit Analysis for Radwaste Systems-for Light-Water-Cooled Nuclear Power Reactors (March 1976) b From Applicant, Supplement 6 to Environmental Report (October 1975)

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Appendix 1 CALCULATED RELEASES-OF RADIOACTIVE MATERIALS IN GASEOUS EFFLUENTS FROM WASHINGTON NUCLEAR PROJECT, UNITS 3 AND 5 Ci/yr/ unit Waste Gas Condenser Processing Reactor Auxiliary Turbine Air Nuclide System Bldg Bldg Bldg Removal Vent Total Kr-83m a

a a

a a

a Kr-85m a

1 2

a 1

4 Kr-85 260 1

a a

a 260 Kr-87 a

a 1

a a

1 Kr-SS a

2 4

a 2

8 Kr-89 a

a a

a a

a Xe-131m a

3 a

a a

3 Xe-133m a

7 a

a a

7 Xe-133 a

570 33 a

21 620 Xe-135m a

a a

a a

a Xe-135 a

6 4

a 3

13 Xe-137 a

a a

a a

a Xe-138 a

a 1

a a

1 I-131 a

2.1(-3) 4.3(-3)

2. 4 (-4) 2.7(-3) 9.3(-3)

I-133 a

8.3(-4) 6.2(-3)

3. 4 (-4)

3. 9 (-3) 1.1 (- 2)

Co-60 7(-5)b 4.7(-5) 2.7(-4) a a

3. 9 (-4)

Co-58

1. 5 (-4) 1(-4) 6(-4) a a

8. 5 (-4)

Fe-59

1. 5 (- 5) 1(-5) 6 (-5) a a

8.5(-5)

Mn-54 4. 5 (-5) 3 (-5) 1.8(-4) a a

2. 5 (-4)

Cs-137 7.5(-5) 5.3(-5) 3(-4) a a

4. 3 (-4)

Cs-134

4. 5 (-5) 3 (-5)

1. 8 (-4) a a

2. 5 (-4)

Sr-90 6 (-7) 4. 2 (-7) 2.4 (- 6) a a

3. 4 (-6)

Sr-89 3.3(-6) 2.4 (-6)

1. 3 (-5) a a

1.9 (-5)

C-14 7.2 8 (-1) a a

a 8

H-3 a

380 380 a

a 760 Ar-41 a

25 a

a a

25 a = negligible compared to overall source term, e.g.,

less than 1.0 Ci/yr noble gases, less than 1 (-4) Ci/yr iodine, b = exponential notation--7(-5) = 7 x 10-5

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Appendix 2 CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN LIQUID EFFLUENTS FROM WASHINGTVN NUCLEAR PRO.1ECT, UNITS 3 AND 5 Nuclide Ci/yr/ unit Nuclide Ci/yr/ unit Cr-51 8(-5)*

Te-131m 4 (-5)

Mn-54 1(-3)

Te-131 2(-5)

Fe-55 1(-4)

I-131 5.9(-2)

Fe-59 5(-5)

Te-132 4.4(-4)

Co-58 4. 9 (-3)

I-132 2.5(-3)

Co-60 8.8(-3)

I-133 3.7(-3)

Br-83 8 (-5)

I-134 3(-5)

Rb-86 2(-5)

Cs-134 2.7(-2)

Sr-89 2(-5)

I-135 1.1(-2)

Mo-99 1.6 (. 3)

Cs-136 2.8(-2)

Tc-99m 1.6(-3)

Cs-137 3.4 (- 2)

Te-127m 1(-5)

Ba-137m 9. 7 (. - 3) 1 Te-127 2 (-5)

Np-239 7 (-5)

Te-129m 6(-5)

All Others Except H-3 6(-5)

Te-129 4 (-4)

Total 2.1(-1)

I-130 1.7(-4)

H-3 7.6(+2) f a = exponential notation: 8(~5) = 8 x 10-5 e

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1 Appendix 3 PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCULATING RELEASES OF RADI0 ACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS FROM WASHINGTON NUCLEAR PROJECT, UNITS 3 AND S Reactor Power Level (MWt) 3800 Plant capacity Factor 0.80 Failed Fuel 0.12% (a)

Primary System Mass of Coolant (Ibs)

S.4 x 10 Letdown Rate (gpm) 84 Shim Bleed Rate (gpm) 1.1 Leakage to Secondary System (1bs/ day) 100 Leakage to Containment Building b

Leakage to Auxiliary Buildings (1bs/ day) 160 Frequency of Degassing for Cold Shutdowns 2

(per year)

Secondary System 7

Steam Flow Rate (Ibs/hr) 1.7 x 10 4

Mass of Steam / Steam Generator (1bs) 1.6 x 10 5

Mass of Liquid / Steam Generator (1bs) 1.6 x 10 6

Secondary Coolant Mass (1bs) 2.8 x 10 3

Rate of Steam Leakage to Turbine Bldg (1bs/hr) 1.7 x 10 Fraction of Feedwater Processed Through Condensate Demineralizers 0.6 5

Steam Generator Blowdown Rate (Ibs/hr) 1.7 x 10 3

6 Containment Building Volume (ft )

3.4 x 10 Annual Frequency of Containment Purges (shutdown) 4 Annual Frequency of Containment Purges (at power) 20 "This value is constant and corresponds to 0.12% of the operating power fission product source term as given in Regulatory Guide 1.BB,,

September 9, 1975.

b 1%/ day of the primary coolant noble gas inventory and 0.001%/ day of the primary coolant iodine inventory.

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Appendix 3 (Cont'd),

Iodine Partition Factors (gas / liquid)

Leakage to Auxiliary Building 0.0075 Steam Generator 0.01 Leakage to Turbine Building 1.0 Main Condenser / Air Ejector (volatile species) 0.15 Decontamination Factors (liquid wastes)

Floor Drain Wastes, Laundry and Boron Recovery Inorganic Chemical Wastes, Hot Shower System (BRS)

Regenerant Solutions Drains 4

4 I

1 x 10 1 x 10 1

4 5

Cs, Rb 2 x 10 1 x 10 g

5 5

Others 1 x 10 1 x 10 1

All Nuclides Except Iodine Iodine 4

3 Radwaste Evaporator DF 10 10 3

2 BRS Evaporator DF 10 10 Aniens Cs, Rb Other Nuclides Boron Recycle Feed Demin. DF (H B0 )

10 2

10 3 3 I'rimary Coolant Letdown Demin.

DF (Li B0 )

10 2

10 3 3 Lyaporator Condensate Polishing Demineralizer (H+0H") DF 10 10 10 Mixed Bed Condensate Demin.

10 2

10 Turbine Air Removal System and Containment Building Internal Recirculation System Charcoal Filter DF (Iodine Removal) 10 Fuel Handling Building and Auxiliary Building Ventilation System Charcoal Filter DF (Iodine Removal) 10

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