ML19289G100

Interrogatories for Nrc.Affidavits Are Requested to Answer Questions on Activity Level & Isotopic Content of Water,How Quantities Are Established,Monitoring Sys & History of Discharges

ML19289G100
Person / Time
Site:	Crane
Issue date:	05/22/1979
From:	LANCASTER, PA
To:
Shared Package
ML19289G099	List: ML19289G098 ML19289G100
References
NUDOCS 7906260308
Download: ML19289G100 (2)

Text

.

G. Knighton May 22, 1979

~-

MEETING WITH NRC SOLICITOR CONCERNING CITY OF LANCASTER CIVIL ACTION In order to respond to the subject civil action, the Solicitor's Office requests affidavits to be prepared which will contain the information ge.lerally reuuired to respond to the following questions.

1)

Quantify and categorize by volume, point of storage, activity level and isotopic content the radioactive water inventory at TMI 2.

2)

Indicate how these quantities were established.

3)

Describe the monitoring systems used to protect the public from these radioactive quantities.

4)

Describe the relationship these volumes of radioactive water can have with the river, including the monitoring of d' inking water, intake points and readings to date.

'S 5)

Describe any systems for future monitoring of the intakes.

6)

Discuss where the City of Lancaster gets its water.

7)

Include a history of dischcrges to the river, both pre-accident and post-accident.

8) Describe the relationship between NRC and the utility with respect to water treatment system design and discharges for post-acc; dent conditions.

M 25i Zh3 7 9082 sosor l

_ 5)

Include a description of the normal plant discharges permitted by tne lic ense as considered in the FES.

10) Provide a chronological breakdown in terms of discharges post-accident, Units 1 and 2.

11) Present a history of any meetings NRC has had with the City of Lancaster on discharges and the position NRC presented.

12)

Discuss Part 20 limits and how they apply to the treatment and discharge of the radioactive water produced by TMI 2 (post-accideni).

13) Provide a description of EPICORs 1 ar., 2 (p roces ses ).

14) Discuss the development of EPICOR 2 design with respect to the TMI incident. Was it designed for TMI 2 incident radioactive waste process?

15) Describe what the plan is for consideration of options, design of system and approval for the high level waste treatment and discharge.

16) Describe present plans for NRC approval for tpicore 2 to assure safety prior to any radioactive waste processing.

17) Describe at what point delay in treatment r discharge of radioactive waste will create safety ir:plications.

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2)

Indicate how these volumes were established.

Res ponse The actual volume of liquids in the tanks are established by plant per-sonnel reading the tank liquid levels off of instruments located in a panel in the auxiliary building.

The liquid levels are then coverted to volumes using conversion tables based on the geometry of each tank. The radioactivity concentrations are determined by direct sampling of the tanks.

The tank water is nixed to provide a representative sample, then drawn into a sampling basin. The sample is then counted on a system which providas the isotopic breakdown of the radioactivity.

The radioactivity concentration of the primary coolant liquids has been determined by analysis of samples taken frcm the primary coolant system.

The quantity of radioactivity in the coolant systen was then cal:ulated based upon the known volume of the primary coolant systen.

The quantity of liquid in the reactor building floor has been determined by measuring the actual liquid level in the reactor building and calcu-lating the liquid volume from that level based upon the known physical No arrangement of reactor building internal structures and components.

samples of the liquid on the reactor building floor have been taken to directly determine the curie quantity in the water. Although no direct radioactivity measurements have been made, the radioactivity concentration should be less than the primary coolant concentrations which have been measured.

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s 3)

Describe the monitoring systems and features used to protect the public from these radioactive quantities.

Response

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As an integral part of the, Liquid,Radwaste Treatment 39' stem at TMI, monitor-

}

ing systems, sample analyses programs, plant procedures and system design features provide protection against the accidental release of unauthorized quantities of radioactivity in liquid effluents to the Susquehanna River.

All liquid discharges from TMI are on a batch basis.

Sample analysis programs stipulated in plant operating procedures require that tank and sump liquids be analyzed and determined to be in conformance with release limits prior to being pu..ved into the discharge line for release to the river.

This analysis includes an isotopic breakdown for specific radio-nuclides. All plant procedures relating to effluent discharges from the plant have been reviewed by the NRC staf f and TMI operations personnel are required to notify NRC prior to beginning any liquid release to the river.

In addition to process radiation monitors, which are designeo to provide information about radioactivity levels in liquids being routed within Lhe plant, effluent release monitors continuously monitor liquid as it is being discharged from TMI.

Automatic termination.of radwaste system liquid discharges is initiated by monitor RML#6 when preset activity limits are exceeded. An additional radioactivity monitor, RML #7, provides backup alarm capability to RP. f 6 and also monitors the common plant effluent from Units 1 and 2 (,

e., induri. rial treatment and tilter system and second-ary neutralizer tank liquid discharges). Alarm and termination set points as well as monitor calibration and operating requirements are set forth in 9

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2_

In order to the operating technical specifications approved by the NRC.

reverify that radioactivity levels are below relense limits, samples are drawn during the discharge procedure and analyzed.

It should be noted fur-ther that the Pennsylvania State Bureau of Water Quality has also placed a mnitor and sampler on the TMI discharge line in order to acquire their own independent analyses of radioactive releases to the Susquehanna.

Tne components and overall design of the liquid radwaste treatment system (both existing and to be completed) have been reviewed by the NRC staff.

Design guidance for components and system design have been published by the NRC in Reg Guide 1.143 and NUREG-75/037. Construction, additional planning and operation invohing supplemental portions of the ra jwaste system (EPICORI& ) are continuing to receive careful review by NRC staff on duty at TMI.

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7.

Question:

Include a history af discharges to the. river, both pre-accident and post-accident.

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e, Resconse:

A surrary of liquid releases occurring during the period 3/28-5/11/79 and a comparison to releases occurring prior to the accident are shown in Table 1, attached.

Table 2 also includes a comparison of the resultant environmental impacts and doses to the public.

See also the response to Question 10.

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Table 1 l

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TMI EFFLUENT WATER RELEASE FOR THE PERIODS 3/28/79-5/11/79 vs 3/28/78-5/11/79 131 3

TOTAL VOLUME TOTAL 7

H RELEASED ACTIVITY ALTIVITY ACTIVITY YEAR (GALS)

'(Ci)

(C1)

(Ci)

J 1978 13 Billion 16.#036 MDA 15.87f d

0 1979 31 Billion 12.733

0. M9 12.47/

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COMPARIS0NS OF DOSES TO MAXIMUM INDIVIDUAL DRINKING TREATED SUSQUEHANNA' RIVER WATER DOWNSTREAM OF TMI*

Columbia i

Intake Actual Upstream Control Environmental Dose from Actual Calculated From Sample

$ Measure.nents in Release Data Pathway Downstream Dose The Environment Downstream Dose 45 Day and Critical 3/28 to 5/11_

3/28 t_o 5/11 3/28 to 5/11_

Natural Nuclide Organ 1979 1978 1979 1979 i-

Background

mrem mrem mrem i-mrem ogny,n9 Thyroid

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<0.05

<0.04 0.on none t

, 3 33 1 0.002 0.002 0.002 3 x 10-5

.0004 ogg3 wge 3

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.00001 Fish, 3H Body

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• Boating, 131 Whole 4.7 x 10 42 x 10 1 x 10-6 3 x 10 None 7

Body x

(

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• Allowable Technical Specification dose for the period 3/28 to 5/11/79 is 0.6 mrem for all pathways and nuclides.

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Question:

-10., ~ Provide a chronological breakdown in terms of dischacce

'a.

Units 1 and 2.

Response

4 No water from within the Unit 2 containmen or primary system has been processed or released, since the water still contains relatively large concentrations of radioactivity.

Presently, the NRC has approved a TMI procedure which permits the release of liquids containing low or non-detectable levels of radioactivity; the water that has been released Jsing this procedure has originated mainly from Unit 1, which was not, involved in the accident. A listing of all liquid discharges from the TMI site c,an be found in Table 3, attached.

See also the response to Question 7.

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., i Release Rat.es Frotn. THI..

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Total Release:

4,993,660 gal.

Averanc Per Release,:

222,890 gal.

Average Per Day:

96,03).9 gal.

TMS :

t?.N' y; %

Total Release:_

962,830 gal.

%,. ~ - ;

Average Per ReIcnse:

57,742.5 gal.

Average Per Day:

17,362.1 gal.

t

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Total Release:

364,659 gal.

Average Per Re}cese:

4,190.5 gal.

Average Per Day:

3',366.5 gal.

.).

s Sec. Neut*:

~

3,310,341 gal.

Total ReJ ease:

s Average Per Re3 case:

63,700.8 gal.

Average Per Day:

25,198.87 gal.

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f 12)

Discuss Part 20 limits and how they apply to the treatment and discharge of the radioactive water produced by TMI 2 (post-accident).

Resoonse The regulatory requirements of 10 CFR 20.106 state that a licensee shall not i

release to unrestricted areas radioactive raterial in concentrations which exceed the limits specified in Appendix B, Table 2.

(Column 2 of Table 2 presents the applicable limits for liquid releases.)

It also states that the concentrations may be averaged over a period not to exceed one year for purposes of compliance.

These concentrations represent potential en-vironmer al doses equivalent to tne maximum allowable limits for members of the general public (i.e., 500 mren, whole body).

These potential doses are calcu ated assuming an individual continuously l

consumes 2.2 liters of water per day at the concentrations presented in the table.

As discussed in item 9), TMI-2 is limited for releases to the Susquehanna River to the concentrations of Appendix B, Table 2, Column 2, on an instan-taneous basis. No allowance is made for averaging; TMI-2 cannot discharge liquids which are in excess of these concentrations. hherefore, TMI-2 must process liquid waste and/or discharge liquids in such a manner not to exceed the concentration limits) Again, as discussed in item 9), the additional li,mit of 10 Curies per quarter represents potential environmental doses which are a small fraction of the maximum allowable and as such is more restrictive ir a general sense than the concentration limits of 10 CFR 20, Appendix B. Table 2, Column 2.

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4 ITEM 13.

Provide a description of EPICORs 1 and 2 (Processes).

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RESPONSE

EPICOR I PROCESS EPICOR I is it portable liquid radwaste processing system which is used to process low activity level liquid radwaste generated from both Unit 1 and Unit 2.

Waste which is acceptable for processing in EPICOR I is any waste which has I-131 concentration of 1 uCi/cc o[less. The system is located in a fenced area, west of the 'Jnit I auxiliary building. The system consists of a filter and mixed bed demineralizer, in series, and two downstream 20,000 gal. collection

~lr tanks in parallel. All waste which is processed through the system is fed from the Unit 1 liquid radwaste system. Processed waste is collected in one of the 20,000 collection tanks for sampling and analysis.

If analysis indicates that the processed waste is suitable for discharge, the waste is directed back to the Unit 1 liquid radwaste system for ultimate disposition. Waste which is found not suitable for discharge is recycled back througt. the' system and collected in the other 20,000 collection tankg. The recycle process is repeated until sampling and analysis indicate the waste is suitable for discharge.

EPICOR II PROCESS a-EPICOR II is a newly constructed liquid radwaste processing system which is designed to process intermediate activity level liquid radwaste collected in Ur.it2liquidradwastesystemKtanks. Waste which is acceptable for processing,

in EPICOR II is any waste which has an I-131 concentration of approximately 100 uCi/cc or less. The system is locat?d in the chemical cleaning buildi1g 2b2 b

7

~

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and consists of a filter and two mixed bed demineralizers, in series,4,u( /v. c/,u-

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_ (133,000 ga-1.. and 95,000 gal.).- The system-interface with the Unit i liquid

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radwaste system, the Unit 2 liquid radwaste system and the fuel pool storage

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sys+em. Liquid waste from Unit 2 will be processed through the filter and two demineralizers and collected in the 95,000 gal. collection tank for samplino e n fa:.a

c. ~ < < ~ lt~ f: * - s and analysis.

If analysis indicates that the processed waste is-suiutde-for

ff, rad:saJ,;/, /LJ me rufhae ~Hy "be directed to the Unit 1 liquid radwaste system for

. 4+scharge, the waste will f

d:se.;+s.s ultimate disposition.

Processdd wasta which is not suitable for discharge can be recycled back through the system or transferred to the Unit I liquid

.radwaste system for polishing i.i EIPCOR I where the waste will te cycled de t...; k.~

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until it is suitable for. discharge. AM-discharges-will be done through the Unit 1 iiquid radwaste system.

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Describe at what point delay in treatment and discharge of radioactive waste will create safety implica. ions.

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Response

As of May 20, 1979, the water level in the containment was estimated to be about 2 feet below the RHR motor-operated isolation valve @DHV-2). Sub-

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mersion of the valve motor would render the valve inoperable and impair the RHR operation.

This could create a safety concern in that it decreases the options available for RCS heat removal, The present leak rate in contain-ment is estimated at about 1 gpm.

For this leak rate, the rise of water is expected to be from 1/4" to 3/8" per day.

If the leak rate does not substantially change, the water level could reach the RHR isolation valve in about two ranths, at whicn point further delay in drainage of water from the containter:t could create safety concerns.

If the water is withdrawn from the containment, two options are available:

on-site storage or processing and discharge. On-site storage creates a number of considerations, such as available tankage capacity, accidental spillage and possible increase in radiation exposure to plant personnel.

Furthermore, the question of disposal of the waste water has to be eventually If the resolved as the inventory accumulates from other waste water sources.

option of processing and discharge is chosen, the radioactivity will be monitored prior to discharge. The radioactivity will be below the NRC regulations limits and will meet the EPA drinking water standard for public water supply.

Under these liminations, the radioactivity releases to the environment after treatment should not be significantly different from those allowed to be routinely discharged from the site prior to the accident, which were evaluated in the FES.

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INFORMATION TO RESPOND TO GENERAL COUNSEL QUESTIONS LANCASTER CIVIL ACTION Question 4 (Intent / meaning of first part is unclear.)

Relationship of discharges with river?

_I_f water is discharged at MPCw from TMI (50,000 gpm)

Assume averaze river flow of 34,000 cfs 4

The downstream mixed river concentration is (7.48 gal /ft ) (60 sec/=in) (34,000 cfs) ' l.53E7 gpm dilution I 50,000 gpm = 305:1 Downriver concentration 0.37. MPCw during discharge Mean Rance of River Flows fro = USGS 41 year average flow 35,390 cfs low flows:

7 d ay - 2 yr, 4100 cf s ; 7 d ay - 10 yr,, 2400 cis 3000 cfs 30 d ay - 2 yr, 5200 cf s ; 30 d ay - 10 yr,

high flows:

7 day - 2 yr, 172,000 cfs; 30 day - 10 yr, 280,000 cfs 30 day - 2 yr,106,600 cfs; 30 day - 10 yr, 157,000 cfs River Flows 1932 - 1971 (Percent of time that flow is greater than)

Percentiles 2

5 10 20 30 40 50 60 70 80 90 Flow (cfs) 160K 110K 81K 54K 38K 28K 21K 16K 12K 8.3K l 5.4K 95 98 Percentiles 4.2K 3.3K Flow (cfs)

RIVER SAMt' LING Agencies:

EPA, PAD",.ai, NRC, Met-E'd NRC:

(1) Selected River, grab samples; analyzed by NRC on TMI site.

(2) Selected grab samples from discharge points.

(3) Weekly independent sampling and analysis of each type of sump or tank being discharged, comparison of results with licensee.

(4) Analysis of every fourthI'JFS and IWTS grab sample;

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0 comparison of results with licensee.

(5) Daily coruposite effluent sample taken from the radiation monitoring pit (RML-7) split with the licensee / contractors.

EPA:

(1) Daily analyses ' water from Brunner Island and Lancaster Water Supply Co. intakes; weekly analyses of water from City Island intakes.

(2) Analyze discharge samples from 1 to 6 ef fluent points collected daily by Pa. DER.

(5) Have cont nuous radiation monitor and composite sampler af discharge 001.

Pa.DEh:

(1) Collection of water sacples daily (EPA analysis).

(2) Selected analyses of samples by Pa DER.

(3) Monthly sample analyses frca Columbia, York Haven, and Steelton.

M yland: (1) Analyses of composite samples at Holtwood, Conowingo, Dats.

(2) Selected water sample analyses from river and discharge points.

Met Ed:

Daily sacples are taken from the following locations and analyzed for I-131, gross beta, gamma emitters and H-3 in addition to routine Sr-89 and 90.

MET-ED SAMPLING LOCATIONS Downstream 9A2 0.5 mi S. of site discharge - composite / split with AC 931 1.5 mi S. of site, above York Haven Dam - gra'o 8B1 4.1 mi S. at Brunner Island - grab composite 7C1 15 mi SE at Columbia Water Treatment Plant - composite 8C2 2.3 mi SSE of site - York Haven Hydro - composite Unstream IC3 2.3 mi N. of Site at Swatara Creek - grab 15F1 8.7 mi ?M of Steelton Municipal Water Works - grab composite

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Samole Results:

Samples analyzed to date by the Pa DER and Federal agencies have not shown any detectable activities above the normal back-ground levels. Met Ed sample analyses have shown some slightly elevated I-131 levels (max. at about 1 pCi/1) in several of the Susquehanna River samples. The majority of the identified elevated levels were found at the Swatara Creek mouth, upstream o f TMI.

No other nuclides have been identified outside their normal background range.

Below are su=marized typical Susquehanna River measurements reported by Met Ed prior to 1979.

River Padiological Measurements (Met-Ed Data)

Ra-226 1.3 - 2.0 pCi/1 (upstream and downstream)

K-40 up to 14 pCi/1 Zr-Nb-95 Max 4.4 pCi/1 after 76 Chinese test H-3 generally less than 300 pCi/1, max in 1978 5430 at 931 I-131 less than 0.2 pCi/1 Question 5 Sy s t ems for future monitoring of intakes (1) The NRC at present plans no additional independent offsite monitoring of water supplies.

(2) Met Ed is considering the composite sampling and an& lysis of water at the Lancaster Water Supply Co.

(2) Pa DER is also considering Lancaster Water Supply Co. intake for daily monitoring.

Question 6 Source of water for City of Lancaster The City of Lancaster gets its water,from two sources; the Conestoga Creek and the Susquehanna River. According to the 1978 annual report to Pa DER, during 1978 33% of the water from Conestoga Creek and 677, from the Susquehanna. The came Conestoga Creek can reportedly be utilized for up to 40-607.

of the water requirements, dependent on season / river flows.

The Lancaster Water Supply Co. provides bulk water sales to Millersville; to 27,468 individual hook-ups; to 2,270 commercial users and 214 industrial users.

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The Susquehanna River intake for the City of Lancaster is located about 1/4 mile downstream of the City of Columbia water intake. The latter is just below (about 100 yds) the old Rte. 30 bridge across

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the Susquehanna River.

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