ML20195G993

Requests NRC Permission to Dispose of Slightly Contaminated Chemical Cleaning Solution Used in Cleaning of Secondary Side of Steam Generators,Per 10CFR20.302(a).Fee Paid

ML20195G993
Person / Time
Site:	Maine Yankee
Issue date:	11/22/1988
From:	Whittier G Maine Yankee
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0596L-DS, 596L-DS, GDW-88-311, MN-88-112, NUDOCS 8811300165
Download: ML20195G993 (26)

Text

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MaineYankee atuastt Etteinory roa uA%E 5.Nct m2 EDISON DAIVE

• AUGUSTA, MAINE 04330.(207) 622 4868 November 22, 1988 HN-88-Il2 GDH-88-311 i

United States Nuclear Regulatory Commission Hashington, DC 20555 Attention:

Document Control Desk

Reference:

(a) License Number DPR-36 (Docket No. 50-309)

Subject:

Request to Dispose Slightly Contaminated Chemical Cleaning Solution in Accordance with 10CFR20.302(a)

Gentlemen:

Maine Yankee Atomic Power Company (Maine Yankee) currently has an inventory consistino of approximately 10,500 gallons (about 200 fifty-five gallon drums) of chemical cleaning solution used in the cleaning of the Mconda y side of the steam generators. This solution has been found to contain very low concentrations (but nonetheless measurable) of radioactive i

materials, and also contain chemicals categorized as hazardous by EPA.

Since this waste contains low concentrations and small total quantity of radionuclides, Haire Yankee requests NRC permission pursuant to 10CFR20.302(a) to dispose of this material as hazardous waste in accordance with EPA regulations without regard to its radioactive content.

j Disposal as radioactive waste, if deemed acceptable under disposal site i

acceptance criteria would require solidification to a stable waste form, i

thereby increasing the disposal volume by a factor of two.

This option, even if viable, is not consistent with the optimal use of the limited radioactive waste burial volume avaU able.

If approval under 10CFR20.302 is granted to dispose of this cleaning solution without concern to its radioactive content, l

Maine Yankee proposes to contract with a firm licensed by the EPA for the treatment and disposal of this material as hazard)us wastes.

It is our intent i

to have the waste transported, in truckload quant

• ties, to a licensed incinerator for burning and ultimate disposal of the residue as a hazardous waste.

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MaineYankee United States Nuclear Regulatory Commission Page Two Attention:

Document Control Desk HN-88-112 A radiological evaluation, based upon an 11,000-gallon total inventory whose specific activity is the highest of any batch in the inventory, has been completed.

The computer prcgram, IMPACTS-BRC, was utilized to evaluate the radiological impacts of the proposed method of treatment and disposal.

In addition, separate shielding calculations were also performed to further assess the dose in the dominant exposure pathway which was identified as the truck driver transporting the material to the disposal site.

Based upon the analysis presented in the enclosed application (Attachment 1), Maine Yankee requests permission to dispose, on a single time basis, the current inventory of decontamination s>1utions stored in approximately 200 fifty-five gallon drums.

As stated in the application, the activity concentration and total activity is so limited that no individual, either worker or men.ber of the public, will receive a dose that approaches one mrem.

This dose, which is about 100 times less than natural background radiation would be indistinguishable from the normal variations in background radiation levels.

It is well below all limits currently under consideration by the NRC for application to materials which could be classified as Below Regulatory Concern (BRC).

Pursuant to 10CFR170.21, a check in the amount of $150.00 is enclosed.

Very truly yours, HAINE YANKEE ATOHIC P0HER COMPANY h1' Sy d-ncil &

G. D. Whittier, Manager Nuclear Engineering and Licensing GDH:BJP Enclosure c:

Mr. Richard H. Hessman Mr. Hilliam T. Russell Mr. Patrick H.

Sears Mr. Cornelius F. Holden 0596L-DS I

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MaineYankee ATTACHMENT 1 HAINE YANKEE ATOMIC POWER COMPANY APPLICATION FOR APPROVAL TO DISPOSE OF SLIGHTLY CONTAMINATED f

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CHEMICAL CLEANING SOLUTIONS 4

h INTRODUCTION i

Haine Yankee has generated an inventory of approximately 10,500 gallons of chemical cleaning solution as a result of cleaning the secondary side of its l

l three steam generators to improve heat transfer and reduce the potential for

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tube failure.

Eight batches of solution were generated in the process of chemically cleaning the secondary sides of the three st m generators.

Three batches had no detectable activity, and the remainder had activity levels in l

the 7E-07 uCi/mi range for gamma emitters when counted for 3,000 seconds.

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l Changing regulations at radioactive waste disposal sites have made future l

disposal of mixed wastes (both chemically hazardous and r.dioactively l

j contaminated) problematical at best.

Disposal as radioactive waste will j

require chemical treatment and solidification to a stable waste, thereby i

i increasing the disposal volume by at least a factor of two.

This option, if available at all, is not consistent with utilizing the limited radioactive waste burial volume available in an efficient manner, f

l A radiological evaluation of processing and disposal as a hazardous waste 7

has been conducted using guidance provided by the NRC Policy Statement, i

l published in Federal Register, Volume 51, No. 166, Page 30839, on August 29, 1986.

Based upon the results of this evaluation and conditions of

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processing and disposal presented herein, Maine Yankee Atomic Power Company

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requests authority under 10CFR20.302(a) to disposa of the slightly

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contaminated chemical cleaning solution in the same manner as noncontaminated I

t chemical cleaning solution of the same type.

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MaineYankee SAMPLE ANALYSIS l

The objective of the chemical cleaning was to remove accumulated tubesheet j

area oxide deposits (sludge). The chemical cleaning process used was a slightly modified version of the Steam Generator Owner's Group (SGOG) process developed by EPRI.

The process consisted of alternate iron solvent and copper solvent steps.

The same process sequence was used to clean each of the three generators as follows:

Checkout Rinse 2 Iron Steps

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2 Copper Steps l

1 Iron Step

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2 Copper Steps j

Final Rinse / Passivation The chemical cleaning process removed about 800 lbs. of sludge from the tubesheet area of each steam generator. The watar lance operation removed an additional 550-1,230 lbs. of sludge from each steam generator.

The total

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sludge removed ranged from 1,290 lbs. for Steam Generator No. 2 to 2,105 lbs.

l for Steam Generator No. 3.

Table 1 summarizes the composition of the waste j

solution generated from the cleaning operation.

Eight separate batches of waste chemicals were generated during the process of secondary side steam generator (SG) cleaning.

Each batch was mixed and sampled prior to transfer to one holding tank. One-liter samples from I

l each batch were counted for 3,000 seconds by a Ge:Li) gamma spectrometer and analyzed for the presence of gamma-emitting radionuclides.

The sample size and counting timas resulted in Lower Limit of Detection (LLO) limits in the range of IE-07 uCi/ml for the radionuclides of interest.

In thres of the i

l batch samples, activity levels were below the LLO.

The highest activity f

measured (see Table 2) in any batch for any radio'tuclide was Co-60 at 7.39E-07 uCi/ml, for purposes of this analysis, it is assumed that the specific activity of the total inventory is at the highest measured activity for all radionuclides detected.

Co-60, Zn-65, and Cs-137 were the only identified radionuclides.

Table 3 lists the total radioactivity inventory assumed in the waste.

s MaineYankee PROPOSED DISPOSAL METHOD i

i It is proposed that the slightly contaminated chemical cleaning solutions be disposed of as a hazardous waste without regarj to its radioactive content.

It is proposed to utilize the services of an EPA licensed contractor I

who will pick up truck load quantities of the druamed waste at our facility and transport the material to his licensed incinerator with no intermediate

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stops for transfer. At the time of incineration, our wastes may be commingled with other wastes in a blending process for efficient combustion, t

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Y ASSUMPTIONS AND ANALYTICAL METHODS j

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i The computer code, IMPACTS-BRC, calculates radiological impacts by i

exposure pathway, and within each pathway, impact by radionuclide.

Past f

experience with this program has indicated that the radiological impact is

)l dominated by the transportation pathway, which in turn, is controlled by gama

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emitters exclusively. One could estimate concent.ations of nongamma emitters l

using methods appropriate for disposal under 10CFR61, but experience has shown j

in every case that the radiological impact of non;amma emitters estimated to l

i be in a waste stream to be at last three orders of magnitude below the l

measured gama activity level.

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l In order to bound the dose assessment, the highest individually measured radionuclide concentration was assumed to represent that radionuclide j

concentration in the entire inventory.

The total activity is determined by j

multiplying the total volume by each specific activity and summing up the l

l products.

The conservative generic default values in IMPACTS-BRC for the f

incineration / hazardous waste treatment and dispossi option were assumed for l

input and are listed in Table 4.

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SUMMARY

AND ANALYSIS OF RESULTS i

For purposes of this analysis, it was assumed that the inventory of i

200 drums could be transported in three truck loads.

IMPACTS-BRC calculates the transportation impact at 9.24E-03 mrem. The program internal assumption f

is a. travel distance of 100 miles.

If one assumes a travel distance of i

3,000 miles and four shipments, the impact is estimated to be no more than 3.7E-01 mrem.

Separate shielding calculations for the dose to the transport

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driver indicate that the value from Impacts-BRC is conservative. As a result, l

waste transporation represents the limiting exposure pathway, with the next most important pathway, the incinerator worker, calculated to be only 9.0E-03 i

mrem.

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The maximum dose of 3.7E-1 mrem which would be received by the transport l

driver, when it is assumed the drums are shipped across country in four l

shipments, is 50 times less than the 20 mrem the driver would receive from making four round trip cross country flights.

The magnitude of the reported impacts 's so trivial that refinement by use of actual site-specific valuss rather thal default values would not alter the l

I conclusion that the radiological impacts are below regulatory concern.

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8100ESTED RELEASE LIMITS l

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The following release criteria are requested to ensure that the

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l radiological impact will be below regulatory concern, and that disposal of the current inventory of chemical cleaning solution as a hazardous waste by 1

incineration and burial of the residue will be allowed without regard to its radioactive content.

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A - Total volume not to exceed 11.000 gallons.

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8 - Specific activity of measured radionuclides not to exceed:

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Co-60 7.5E-07 uCi/cc Zn-65 6.2E-07 uC1/cc i

Cs-137 1.9E-07 uC1/cc C - Total activity of measured radionuclider act to exceed:

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Co-60 32 uCi Zn-65 26 uC1 Cs-137 8 uCi l

COMPLIANCE GUIDELINES i

The procedures and methods described in Appendix 1 will be implemented by I

incorporation into approved plant procedures to ensure that release limits described herein will not be exceeded, f

1 LICENSE AMENOMENT INFORMATION

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A review of the plant operating license has indicated that there are no j

l additional license amendments required to dispose of this waste material in j

the requested manner.

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s MaineYankee TABLE 1 Sludge Removal SurMAr3 Sludge _ Removed (1bs.)

EG_fio,J SG No. 3 SG No. 1 Pre-Cleaning Sludge Lance:

436 1,078 1,038 Chemical Cleaning:

Fe 508 555 501 Cu 116 147 131 Zn 43 41 42 Ni 13 18 15 Filtered Solids 54 111

_._ 8 4 Subtotal 736 872 773 Post-Cleaning Sludge Lance 118

_.155

_201 Total Sludge Removed 1,290 2,105 2,012 L

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t MaineYankee TABLE 2 Highest Activities Measured in Anv Samolt Specific Activity Radionuclide (uC1/ml)

Co-60 7.39E-07 Zn-65 6.12E-07 Cs-137 1.76E-07 i

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MaineYankee TABLE 3 Assumotions and Conversions Total Activity Radionuclide uti Co-60 19.37 Zn-65 24.32 Cs-137 6.99 Density of Haste Stream - 1 gm/ml Total Volume:

10.500 gal x 3.785E+03 ml/ gal - 3.J74E407 ml Total Hass at I gm/ml - 3.974E+01 metric tonnes Total Radionuclide Activity (from Table 2 and Total Volume) l e

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MaincYankee TABLE 4 IMPACTS-BRC Inout Data (Taoe 5 Inout)

Parameter VAhte Definit' IR - Regional Index 1

Humid, Low Perm. Soil -

Northeast IDAT - Data Index 0

Use Default Values for Region IQ - Disposal Facility Index 5

.iazardous Haste Incinerator /

'andfill II NSTRD - Number of Haste Streams 1

Number of Streams Modeled Under IQ IPOP - Facility Environmental Index 2

Jrban (for Population Exposure Calculations)

ILFE - Disposal Facility Life 20 Years of Disposal Facility Operation IINS - Instrument Control Period 30 Years Between Closure and Loss of Control 10FL - Overflow Index 1

Calculate Impacts of Leachate Overflow ID - Dispersibility Index 3

3evere (Ash, Dirt, Powders)

IA - Accessibility Index 1

)rdinary Haste (Not Activated tetals)

IK1 - First Package Index 0

Not Packaged (For Disposal)

IK2 - Second Package Index 0

(Used Only When IKI - 1)

IP - Processing Index 2

Incineration and Disposal IX) - Distribution Inder 1 3

Number of Shipping Vehicles IX2 - Distribution Index 2 100 Percent Vehicle Load That is De Minimis IX3 - Distribution Index 3 1

Number of Processing Facilities IX4 - Distribution Index 4 1

fumber of Disposal Facilities 0598L-DS

i MaineYankee IMLL4 (Continued)

Parameter Value Definition ICI - Combustion Index 1 100 Height Percent Combustible Component IC2 - Combustion Index 2 0

Height Percent Metal Component IC3 - Combustion Index 3 0

Height Percent Glass Component IC4 - Combustion Index 4 0

Height Percent "Other" Component l

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l APPENDIX 1 I

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COMPLIANCE GUIDELINES r

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MaincYankee Como11ance Reautrements for Secondary Side Steam Generator Chemical Cleanina Haste Liould DisDosal L

I 1.0 PURPOSE j

4 The purpose of these compliance requirements is to provide instructions to ensure that very low-level contaminated liquid waste to be disposed of as l

Below Regulatory Concern (BRC) materials does not result in a radiological impact to any member of the public of more than a few millirem, total 1

exposure.

l 2.0 SCOPE l

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These requirements apply to the steam generator secondary sidc chemical cleaning waste solutions generated at the plant in 1987, and for which NRC i

i rpproval, pursuant to 10CFR20.302(a), is required prior to off-site

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utsposal.

The requirements below only address the controls necessary to f

ensure that the radiological characteristics of the wast, solution will be within the parameters evaluated for potential dose impact as described in i

the application to NRC for approval to dispose of without concern for l

radiological content.

Handling requirements concerning the chemical

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l nature of the waste are not addressed in this outline.

The instructions for the disposal of the chemical cleaning solution as BRC waste address

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the following items:

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2.1 Sampling i

2.2 Gamma Spectroscopy Measurements f

i 2.3 BRC Compliance Determination z

2.4 On-Site Marking and Handling 2.5 Records i

I These requirements are applicable only to off-site combustion in a i

hazard::us waste incinerator and to the disposal of the resultant ash in a

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hazardous waste di;posal facility.

3.0 REFERENCES

I 3.1 Code of Federal Regulations 49CFR173 applicable to shipping of hazardous substances, i

I 3.2 Calibration procedures for radiation dettetton equipment (utility-supplied).

1 3.3 NRC application for approval to dispose of slightly contaminated chamical cleaning solutions.

f 3.4 Code of Federal Regulations 40CFR261 relative to EPA hazardous wastes i

and hazardous waste characteristics.

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i 4.0 PRECAUTIONS AND LIMITATIQ!i$

i 4.1 Contaminated steam generator chemical cleaning waste ligulds I

i containing a total activity concentration of 1.6E-06 uCi/cc or

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greater may not be exempted as BRC material.

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4.2 The annual total quantity of activity contained in the chemical cleaning BRC waste liquid shipped for incineration in a single off-site facility must not exceed.065 mC1/yr.

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5.0 DEFINITIONS l

t The following definitions are applicable to the terms used in these:

Lower Limit of Detectabilit/ as defined by the plant I

5.1 LLO j

Technical Specifications.

i Minimum Detectable Activity defined by:

5.2 HOA 4.66 x BKG MDA -

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E x V x exp (-gt) x 2.22 x 10 xT I

where:

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Count efficiency.

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4 Background, f

BKG Count time.

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Elapsed time.

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V Sample volume.

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Conversion constant.

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Decay constant.

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5.3 Total Activity - The sum of all guna-emitting nuclides.

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j excluding all naturally occurring nuclides, contained in the i

wastes (mC1).

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6.0 lhSTRUCTIONS i

6.1 Samoling of Drummtd Chemical Cleaning Liquid Hastt l

1119 1 If not done at the time of filling, assign an identification number to each drum to be disposed of as i

BRC.

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i 112D_2 Perform a radiation survey :o measure the contact dose l

j rate on each druh. to be included within the drum lot.

l The drums identified within a lot should not have dose l

rates exceeding a factor of 2 from each other.

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4 MaineYankee SteL3 Since all the drums were made up from a single recirculated storage tank, it will only be necessary to do random sampling.

Recirculate and collect a 1 liter sample from 10 randomly selected drums.

Simp _4 Label the samples with the appropriate description, sample numbar, drum number, and date of sampling.

l 6.2 Samoling of Liquid Tankt Sten 1 If mixing capability is available for the tank (s), the tank should be mixed prior to sampling.

Sten 2 Collect three (3) samples from the top, middle, and bottom portions of the tank, or alternatively from a sample connection on a recirculation line if available.

The minimum s 9ple size should not be less than 250 mis.

ittL3 Label the sattples with the appropriate description, sample number, and sampling date.

6.3 Gamma.Sp1ctroscopy He11urementi Sten 1 Count the samples on a high resolution gamma spectroscopy system.

Holt: Count times should be used that are long enough to ensure meeting the following minimum LL0s:

Ce-144 5.QE-6 UCi/gm 2 Hn-54, Co-58 l

Co-60, Cs-134, Cs-137 5.0E-? uCi/gm Note:

If any result varies by more than i 25% from the mean, expand the sample size by another 10 drums.

ittL2 Determi.le the average conce'itration of each of th6 i

quantified nuclides in the counted samples.

Samples with an HOA indicated for a given nuclide should not be used in the average computation.

If there are no I

quan',1fted nuclides identified in the sample, then the i

HDAs for Co-60 and Cs-137 siould be summed for the total activity. The concentrations should be determined in terms of UC1/gm.

0597L-DS

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MailleYankee Sito_3 Sun C on J nuclide concentrations to determine an avr e t io'C activity concentration for the samples.

Sitp_3 Retain the gamma spectroscopy data results' printout and the averaging calculation.

6.4 BRC Comoliance Determination iteal Determine the total volume of contaminated chemical cleaning 11guld intended to be disposed of as BRC waste (not to exceed 10,500 gallons).

Sitp_2 Using the total waste 11guld volume and the average total activity concentration, compute the total activity contained in the waste.

Sitp_3 Verify that the average totil activity concentration does not exceed 1.6E-06 uC1'cc.

$1tp_4 Identify the incineration facility destination for the waste liquid to be disposed of as BRC.

6.5 On-site Markina and Handlina Stepl Drummed liquid waste, if not already tagged, should be tagged with an appropriate color-coded tag with instructions that the drums are not to be opened nor moved without Health Physica approval.

The tag should note that the drum has been sampled and should include the sample number and date.

l S.ttp_2 Assign a number to each of the drums contained in the sampledlot.

Establish an inventory list of the numbered drums.

51eL3 For waste liquid drums ship)ed off-site to a hazardous l

waste incineration facility, remove the Health Physics control and inventory tag.

Replace the tag with a shipping label in accordanca wit 5 DOT Regulations 49CFR173.

Holn:

(a) Radiological loformation need not be included on the shipping label.

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(b) for shipments to a hazardous waste incinerator, prepare shipping papers and/or a shipping manifest in accordance with DOT Regulations 49CFR172.200, 49CFR172.205 and EPA Regulations 40CFR262.

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= e MaineYankee 6.6 Record Dteping Sitp_1 Establish a BRC Haste Disposal Log on a calendar year basis for each incineration facility locations used for BRC disposal. The log should contain, as a minimum, the following information:

a.

Incineration facility location and facility description, b.

Disposal facility location and facility description i

(if different from Iten a.

c.

BRC shipment number assigned.

d.

Shipment or transfer date.

e.

Haste liquid volume in shipment or transfer.

f.

Total activity in shipment, g.

Year-to-date waste volume shipped to facility.

h.

Year-to-date cumulative total activity shipped to disposal facility.

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Name of waste hauling company or entity.

Sita_2 Establish a records file fo.* each shipment of BRC waste liquid. As a minimum, the file should contain the following information:

a.

Shipment number.

b.

Shipment date.

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Shipper's certificate (if applicable).

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d.

Sample gama spectroscopy results' printout.

e.

Haste description and classification.

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Shipping papers.

g.

Nuclide average and suwnation worksheet.

h.

Haste volume, mass, anl total activity worksheet.

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MaineYankee APPENDIX 2 IHPACTS BRC INFUT AND OUTPUT FILE LISTING i

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