ML20245C944

Forwards Summaries of Ongoing Research Projects & Development of High Level Waste Mgt Research Needs,Per 890608 Request

ML20245C944
Person / Time
Issue date:	06/21/1989
From:	Chery D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Ballard R, Bunting J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
REF-WM-1 NUDOCS 8906260334
Download: ML20245C944 (52)

Text

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v HLWM RESEARCH NEEDS JUN 211989 MEMORANDUM FOR: Ronald L. Ballard, Chief Geosciences and Systems Performance Branch, HLWM Joseph 0. Bunting, Chief Engineering Branch, HLWM FROM: Donald L. Chery, Jr., Section Leader Hydrologic Ttansport Section Geosciences and Systems Performance Branch, HLWM

SUBJECT:

SPECIFIC HLWM RESEARCH NEEDS As you requested in your memorandum of 6/8/89, I have had staff preparing summaries of the ongoing research projects and developing research needs according to the format of the forms attached to your meorandum. I assigned staff to follow each of the ongoing research projects as idicated in  !

Attachment I.

I have attached (Attachment 2) an initial set of ongoing research summaries.

I am not satisfied with some of the summaries and will have them revised and submitted later. I would also appreciate any comments that you may have on the prepared summaries.

I have also attached (Attachment 3) an initial set of research needs I statements from the Section. These needs statements have only had my review, l and have not been through the entire process that I planned for.their '

development. Remaining steps are discussion with the entire Section; discussions with the research staff and then deciding on a final set of needs.

S o: Donald L Ch ry, Jr., Section Leader

'- o Hydrolo ic Transport Section S' Geosciences and Systems Performance Branch, HLWM R Attachments:

e As stated e u.i DISTRIBUTION:

Wo oc Central Files REBrowning, DHLWM BJYoungblood, DHLWM RLBallard, HLGP M J0 Bunting, HLEN JLinehan, HLPM HLGP r/f NMSS r/f

.M SCE MSilberberg, WMB PJustus, HLGP W0tt, WMB SCoplan, HLGP JPsandall, WMB TMo, HLGP DChery, HLGP JPohle, HLGP

• " NColeman, HLGP JBradbury, HLGP DBrooks, HLGP WFord,HLGPM) ,f FRoss, HLGP /

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ATTACHMENT 1 ,

1 ASSIGNMENT OF HYDROLOGIC-TRANSPORT STAFF TO ,

FOLLOW ONG0ING RESEARCH

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. . s-3 l HLWM FY 89/90 HLW RESEARCH SUPPORT HYDROLOGY AND GEOCHEMISTRY Hydrology D1662 Unsaturated Flow (U od Az) W. Ford TBD/D1662 Cont. Validation Exp. Unsat. Flow (U of Az) W. Ford G1112 Large Block Grand (U od Az) W. Ford B7096 Climatology of Recharge (CNWRA) N. Coleman D1672 Char. Mod. Cont. Trans. (U of Az) T. Mo Dll63 Flow of Water and Contam. In Fract. N. Coleman Rocks (In Situ, Inc.)

Geochemistry B0462 Valence Effects /Adsorp. (ORNL) J. Bradbury' I B3040 Site Geochemistry (LBL) T. Mo B6644 Unsat. Mass Transport (CNWRA) T. Mo B6773 Lab Modeling of Sorption (CNWRA) D. Brooks  ;

G1150 Hydrochemical Trans. Modeling (J.H.U) J.Bradbury MATERIALS AND ENGINEERING Corrosion D1670 Overpack/ Backfill (NIST)

D1690 Metrology (NIST)

D1692 Overpack Degradation (CorCo)

B6663 Integrated Experiments (CNWRA)

TBD Waste Container Sealing (CNWRA)

Rock Mechanics-D1192 Sealing Boreholes in Tuff (U of Az)

B6643 Seismology (CNWBA)

PERFORMANCE ASSESSMENT MODELLING Modelling A1266 Perf. Assess. Meth. (SNL) J. Pohle B7121 Climates of the Holocene (NSF) F. Ross B6667 Thermohydrologic Interactions (CNWBA) J. Pohle wa.

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'B6664 Stochastic Techniques (CNWRA) J. Pohle G1120 Contam. Trnspt. Modelling (NAS) T. Mo L D2505 Non Linear 2 D Hydro Modelling (SBIR) F. Ross

, TBD Perf. Ass. Modelling(CNWRA)

'Model Validation Data Basses D2012 Alligator Rivers (ANST0/NEA) D. Brooks

'A1824 -Valles' Caldera ~(SNL) J. Bradbury 86673 Geochemical Analogs (CNWRA) J. Bradbury

.TBD Transport Analyses (CNWRA) J. Bradbury i

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ATTACHMENT 2 HYDROLOGIC-TRANSPORT SECTION-SUMMARIES OF ONG0ING RESEARCH

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FIN / TITLE: D1662/ UNSATURATED FLOW, PHASE III i

CONTRACTOR: UNIVERSITY OF ARIZONA

' BUDGET FY89 200K FY90 0 K l FY91 'T R FY92 U"Y l HLWM LEAD: FORD RES LEAD: NICHOLSON-H-T NEED FOR RESEARCH:

'The H-T needs information on or determination of :

1. Unsaturated fractured rock (tuff) flow and transport processes.

2. Unsaturated zone flow and transport models

3. Unsaturated zone vapor phase flow and transport processes, u

4. Unsaturated fractured rock (tuff) vapor phase flow and transport models.

5. Available laboratory and field techniques, and equipment for use in the unsaturated zone investigations; RESEARCH OBJECTIVES (KEYED TO HLWM NEED FOR RESEARCH):

a. Examine the assumption'that the unsaturated flow is controlled i predominantly by matrix flow with ground-water travel times and arrival H time distributions calculable based upon this assumption (Need 1).

, b. Examine the assumption that ground-water chemistry as' sampled beneath the regional water table in the saturated zone is the same as that in the overlying unsaturated zone (Need 1).

c. Examine the assumption that ground water recharge can be determined as the residual of precipitation minus mean evapo-transpiration and runoff (Need j

'1),

i- "This work will emphasize measurements and methods to (1) determine the relative contributions of matrix flow and fracture flow components in the total ground-water flow of an unsaturated fractured system, (2) assess geochemical sampling techniques for the unsaturated zone and (3) determine ground-water flux and travel times for partially saturated nonisothermal systems" (FIN D1662 Statement of Work, 3/27/86).

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-D1662 STATUS OF RESEARCH TO DATE-(KEYED TO RE nARCH OBJECTIVES):

, A thermoelectric cooling technique to collect water quality samples from the unsaturated zone showed some promise under laboratory conditions.

However, the technique requires extensive testing in the field environment (Objective none).

The fractured flow properties of consolidated media cannot be fully characterized using presently available methods (Objective none).

Conclusions on the reliability and utility of standard tensiometer, osmotic tensiometer, soil moisture blocks composed of ceramic, gypsum or nylon, thermocouple psychrometer, filter paper absorbers, electrical-resistivity logging, and neutron logging have been documented (Objective none).

Two pieces of equipment have been developed; a heat pulse flow meter for use in water filled boreholes and a fractured rock infiltrometer (Objective none).

Research results indicate that in order to determine flow paths, and flux rates, in situ water potentials need to be determined (Objective none).

The phenomena of convective air flow in the fractures has been observed (Objective none).

It was found that soil gas concentrations of fluorocarbon tracers, BCF, and F-22, and the sulfur hexaflouride tracer SF6, are suitable chemical tracers for estimating water infiltration rates when infiltration rates are relatively rapid, or the medium is nearly saturated. SF6 was shown to to have characteristics most conservative-(i.e. less M rptive) for field applications (Objective none).

Vacuum lysimeters were modified to sample water from the unsaturated zone when the matrix potential is less than one bar suction. This modification requires an initial injection phase, in which water of known chemical composition is injected into the zone around the lysimeter. After the distilled water is allowed to mix with native waters, a sample is recovered which contains dilute chemical species (Objective none).

Flourescent dyes for use as tracers in fractured rock were investigated.

Three dyes were found to have particular usefulness; Lissaine FF, Rodamine WT, and Amino G acid. Of these three dyes, Amino G acid may prove to be most useful for borehole testing (Objective none).

A review of isotopies and mineralogy indicated that mineralogic, isotopic, and flow hydration paths andvariations at aextent defining the site may be useful of water inputsin(Objective distinguishing) none primary

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, The movement of water vapor away from a heat source in unsaturated l fractured media has been modeled (Objective none).

1 L Counter-current phenomenon has been demonstrated in heater experiments '

(Objectivenone).

A theoretical analysis was performed to identify and evaluate potential mechanisms of radionuclides vapor phase transport in unsaturated fractured rock. -Research findings included:

1. Near repository important transport mechanisms were identified.

Ordinary. diffusion, viscous flow, forced diffusion of. ionized vapor particles, aerosol transport, thermal diffusion and thermophoresis were identified as im near the repository (Objective none)portant transport mechanisms

2. Forced diffusion by an electric field was evaluated by considering two cases: (a) an HLW canister located in a rock I mass, and (b) an HDf canister located in air. For the first case, calculations indicated that the electric fields created within the rock mass would be miw r. Consequently forced '

diffusion would be insignificant. For the second case, the calculation predicted electric fields created in air sufficiently large to result in forced diffusion. Hence, forced

. diffusion may be a plausible pathway whereby radionuclides, present as vapor, could move from the canister across the air

. zone to the rock mass (Objective none).

3. Radionuclides aerosol transport could be a potentially important mechanism near a repository (Objective none).

4. Near a repository, vapor transport mechanisms and processes, either individually or coupled with other transport mechanisms, can provide a means of transport from a failed canister to the geologic medium and possible as far as the zone of higher saturation enveloping the canister or repository regiori (Objective none) 1 An overview (NUREG/CR-5097) of existing conceptual models of unsaturated flow and transport was prepared (Objective none).

A computer model based on the boundary integral method has been formulated to investigate hydraulic and solute transport properties of unsaturated fractured rock. Sensitivity studies showed that: (1) global hydraulic conductivity is linearly dependent on the product of fracture transmissivity and density for fractures of infinite length; (2) increased fracture length and transmissivity increases the global hydraulic 1

conductivity; and (3) simulated flow through a fractured permeable matrix {

compare favorably with analytic results (Objective none).  ?

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j Flow through variably saturated fractures was modeled using a constant capillary head within individual fractures. A simulated free surface j

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. compares favorably with an approximate analytic solution and with  !

, laboratory results. Faster travel times are noted as fractured saturation E

decreases for the fracture network examined _(Ob,iective none).

The following NUREG reports have been completed:

1. NUREG/CR-4654, R.T. Green and D.D. Evans, Radionuclides Transport as Vapor Through Unsaturated Fractured Rock, July, 1987

2. NUREG/CR-4655, T.C. Rasmussen, and D.D. Evans, Unsaturated Flow and Transport Through Fractured Rock Related'to High-Level Waste Repositories, Final Report - Phase III, May, 1987

3. NUREG/CR-5097 T.C. Yeh et al. Simulation of Liquid and Vapor Movement in Unsaturated Fractured Rock at the Apache Leap Tuff Site, March, 1988 4 NUREG/CR-5239. T.C. Rasmussen and D.D. Evans, Fluid Flow and Solute Transport Modeling Through Three-Dimensional Networks of Variably Saturated Discrete Fractures, January, 1989

5. NUREG/CR-5255, D.S. Weber and Evans, D.D., Stable Isotopes of Authigenic Minerals in Variably-Saturated Fractured Tuff, November, 1989 l

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G1112 l FIN / TITLE: G1112/ WATER CONDUCTIVITY AND RADIONUCLIDES TRANSPORT FOR PARTIALLY-SATURATED ROCK ~ FRACTURES (LARGE-BLOCK EXPERIMENTS)

CONTRACTOR: UNIVERSITY OF ARIZONA BUDGET: FY89 78K FY90 78K FY91 - FY92 HLWM LEAD: FORD RES LEAD: NICHOLSON HLWM NEED FOR RESEARCH (LIST):

This research is needed to help the Hydrologic Transport.Section staff evaluate current conceptual models of fracture / matrix flow, which will be used to conduct performance assessment evaluations. These methods have not been experimentally demonstrated by tests on unsaturated fractured rock; requiring performance assessment calculations to rely on theoretically based models and approximations which have not been field or laboratory tested.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

1. Develop techniques for characterizing water flow and radionuclides transport through rock fractures at different levels for saturations or water potentials

2. Relate fracture flow and transport to matrix flow and transport at selected water potentials for a slightly welded tuff formation.

3. Select, prepare, and transport large blocks from the Apache Leap tuff site to the laboratory.

4 Prepare' and instrument laboratory with pressure, and hydraulic devices

5. Initiate experiment starting with saturated - isothermal conditions, i

STATUS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

This project is a grant and there are no deliverables and there have been f no significant findings to date (project began 10/01/87)  !

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B7096 FIN / TITLE: 87096~ / CLIMATOLOGY EFFECTS ON LONG-TERM RECHARGE CONTRACTOR: CNWRA 0 K, BUDGET: FYB9 0 K. FY90 FY91 K, FY92 K HLWM LEAD: COLEMAN RES LEAD: KORNASIEWICZ HLWM NEED OR RESEARCH-(LIST):

To assess compliance with GWTT and EPA Performance Standards

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

To assess long-term effects on Recharge of major Climatic Changes STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

Project has not yet begun.

D1672 FIN / TITLE: D1672/ IMPROVED METH0CS OF CHARACTERIZING AND MODELING CONTAMINANT TRASSPORT HLW CONTRACTOR: UNIVERSI.! 2 ARIZONA BUDGET: FY89 153K, FY90 150K FY91 YDUK, FY92 T K HLWM LEAD: Mo RES LEAD: NICHOLSON HLWM NEED FOR RESEARCH (LIST):

The H-T staff needs criteria methodologies to evaluate transport of radionuclides in anisotropic and unsaturated fractured rocks and validity of calibrated groundwater flow and radionuclides transport models applied to HLW repositories in unsaturated fractured rocks.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

1. Investigate methods of in-situ pump testing for measuring the maximum hydraulic conductivity in unsaturated fractured rocks.

2. Perform theoretical studies to assess the feasibility of heat tracer experiments.

3. Investigate the modeling of non-Fickian transport.

4. Investigate how to account for groundwater velocity related uncertainties in transport modeling.

5. Investigate ways to factor as much site characterization data as possible into parameter estimation by inverse methods. j i

6. Provide technical support for NRCN waste management research agreements '

with other countries.

1 STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

1. Practical considerations of site characterization preclude the  !

implementation of any useful mathematical models of groundwater flow and I contaminant transport in fracture systems visualized as systems of discrete fractures.- 1 l

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' 2. .Models based on.the assumption that fractured media are isotropic porous' media are overly simplified. '

3. A stochastic' continuum approach to represent fractured rock permeability is a'.useful modeling alternative.

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D1163 FIN / TITLE: DI163/ FLOW OF WATER AND CONTAMINANTS IN FRACTURED ROCKS' CONTRACTOR: IN SITU, INC. BUDGET: FY89

• K. FY90 0 K FY91 0 K, FY92 0 K-HLWM LEAD COLEMAN

• ON NO-COST. EXTENSION (END 5/89)

RES LEAD: MCCARTIN-1 HLWM NEED FOR RESEARCH (LIST):

To help assess compliance with GWTT and EPA Performance Standards 4

RESEARCH OBJECTIVE:(LIST AND KEY TO HLWM NEED FOR RESEARCH): '

Investigate theory of flow and transport in saturated, fractured rocks Examine the tensorial nature of dispersion and porosity in sat., fractured rock 4

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVE):

In saturated, fractured media, porosity should be treated as a tensor.

l A high density of monitoring wells is needed to hydraulically characterize geologic structures.

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B0462 FIN / TITLE: 'B0462/ VALENCE EFFECTS / ADSORPTION CONTRACTOR: ORNL BUDGET: FY89 100K , FY90 0K FY91 0 K FY92 0K  !

HLWM LEAD: BRADBURY RES LEAD: BIRCHARD i HLWM NEED FOR RESEARCH (LIST):

The H-T staff needs information on the factors that control radionuclides-valence. states which affect solubility and speciation.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

(1) To identify and understard the factors that control radionuclides valence  !

states under repository tunditions (2) To measure the solubility, speciation and sorption properties of indiv; dual valencestatesoftechnetium(Tc), neptunium (Np),anduranium(U)under projected repository conditins.

(3) To assess laboratory methods of valence state control needed to replicate repository conditions in the laborato:y.

STATUS / FINDINGS 0F RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVE):

1. Determined the solubility under a range of reducing conditions and C1 contents 2.. Identified that certain BWIP investigations of host rock / groundwater

. interactions were seriously flawed.

3. Oxidized valence stated of Np and possibly Tc are reduced in surface mineral interactions not in the water itself.

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_1 :i e-FIN / TITLE: B'3040/ SITE GEOCHEMISTRY CONTRACT 0Ri LAWRANCE BERKELEY LAB l BUDGET: FY89 250 K, FY90 0K- 1 FY91 0 K, FY92 P  ?

HLWM . LEAD: TIN MO-RES LEAD:' BIRCHARD HLWM NEED'FOR RESEARCH (LIST):

This.research is needed to provide information that will be useful to H-T 4taff in its review of DOE's site characterization activities, DOE's: analysis.

of data and. interpretation.in NRC/ DOE geochemistry relicensing meetings for:

the Yucca Mountain project.- ' ~

RESEARCH'0BJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH)':

The o'vera11 objective is to; identify and gauge the relative importance of.

individual hydrochemical' processes controlling radionuclides behavior within

.and close to a geological repository and fonn a basis for evaluating the.

chemica1' evolution.of groundwater and transport of radionuclides. ' Specific objectives are:

'To provide the H-T staff with an audit capability with respect to DOE programs on the geochemical behavior of the "near field" of the HLW repository.

~*To develop physical and chemical data and computer codes to substantiate the technical basis for licensing with respect to predictions of the-behavior of the rock, groundwater and packing material in the repository nearfield.

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVE):

L *Research showed that room temperature thennodynamic data for actinides l :were not sufficient for predicting solubilities at repository temperature. In response, DOE developed a program to address the need for thermodynamic data.

"A model of radionuclides diffusion was shown to be a major transport mechanism through clay packing.

' Major errors were found in the thermodynamic data base used for

. geochemical modeling. The thermodynamic data base for components that make up minerals has been corrected and papers have been submitted to

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1 peer reviewed technical journals. Geochemical models using the corrected data can accurately predict mineral stability at repository temperatures. ,

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2. Models based on the assumption that fractured media are isotropic parous 1 media are too simplified-

.3. A stochastic continuum approach to represent fractured rock permeability is a useful modeling alternative.

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B6644 FIN / TITLE: 86644/ UNSATURATED MASS TRANSPORT CONTRACTOR CNWRA BUDGET: FY89 260K, FY90 260K FY91 N DR, FY92 TT HLWM LEAD: M0 RES LEAD: BIRCHARD HLWM NEED FOR RESEARCH (LIST):

The technical kr.owledge base and the results of geochemical investigations from this research project will provide independent technical support to H-T staff's provision of appropriate, timely relicensing guidance to DOE, its evaluation of geochemical information presented in DOE's licensing submittals and enable the NRC to regulate and make licensing decisions from a completely

. informed technical position concerning the disposal of HLW as required by the NWPAA.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

The general-goal of this research project is to obtain an understanding of geochemical mass transfer processes including sorption and matrix diffusion in both saturated and unsaturated, fractured, and porous tuff.

The specific objectives required to attain the goal of this geochemistry research project are:

Evaluation of unsaturated / saturated, devitrified, fractured tuff, of the DOE conceptual model (CDSCP Section 8.2.1.1) of equivslent-porous-media transport through the matrix with retardation of radionuclides by adsorption or by other reactions such as ion exchange or coprecipitation.

Evaluation of the chemical composition and physical properties (a range of these parameters) for water, cer. au solid phases in unsaturated, fractured tuff under ambient ce d tion ind to evaluate models of the evolution of these phases in tiv 6,:e -J zone of a HLW geologic repository in unsaturated, fractured tuff.

Interfacing with natural analog, hydrological, thermohydrclogical, and waste package research programs at the Center to provide mutual support and to identify and investigate significant coupled processes. i Evaluation of geochemical data bases and computer programs for geochemical modeling used in performance assessment of the high-level waste site, and identify key parameters for which data are lacking or inadequate.

r B6644 Performance geochemical investigations which will help resolve the lack of or inadequecy of available data for key parameters. identified previously.

Assessment of the status of DOE's Nevada Nuclear Waste Storage Investigations (NNWSI) Geochemistry program which are pertinent to the Center's Geochemistry Research Program.

Development and maintenance of an understanding of information currently available in geochemistry which is pertinent to supporting NRC's activities associated with licensing the candidate HLW repository at '

Yucca Mountain.

Continuous maintenance of integration of technical support to NRC and the Center's activities in the area of geochemistry as required by Program Architecture.

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVE):

The results of geochemical modeling using the CNWRA modification of the EQ3/6 code indicate that J-13 well water composition is not representative of the water in the unsaturated zone and may not be suitable for geochemical and waste package experiments.

Based on a literature review the CKd2A found that the current thermodynamics data 5ase for clinoptilolite and clay minerals and tuff i mineral forming elements is not adequate to perform predictive geochemical modeling with an acceptable degree of certainty and confidence.

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L B6773 9

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' FIN / TITLE: 'B6773 / MODELING OF SORPTION l

CONTRACTOR: CNWRA BUDGET: FY89 0 K, FY90 400K, l FY91 K, FY92 K HLWM LEAD: DAVID BROOKS _.

'RES LEAD: GEORGE BIRCHARD HLWM NEED FOR RESEARCH (LIST):

This research'is needed to support the development of guidance to DOE (i.e.,

RadionuclideTransport_T.P).

RESEARCH OBJECTIVES (LIST AND KEY T0.HLWM NEED FOR RESEARCH):

TBD - - No S0W/PDS No CNWRA'Research Plan STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

None.

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' HLWM RESEARCH SUMARY 1

FIN / TITLE: Cel)S4/.My h h [uh b s. AkN CONTRACTOR: Es N.V- BUDGET: FY89 K, FY90 K, FY91. K, FY92 K' j

1 HLWM LEAD: T, T v%

RES LEAD: 1. N W Ad HLWM NEED.FOR RESEARCH.(LIST):

RESEARCH OBJECTIVES (LIST AND KEY'TO HLWM'NEED FOR RESEARCH):

STATUS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

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FIN /TTTLE: 'A1266/ PERFORMANCE' ASSESSMENT METHODOLOGY-

' CONTRACTOR: SANDIA NATIONAL LAB BUDGET: FY89 500K, FY90-500K FY91 IMK, FY92 TT HLWM LEAD: AI. Mh RES LEAD: RANDALL LHLWM NEED FOR RESEARCH (LIST):

'This research is_needed to support the H-T staff's audit capability for the review of-material submitted by DOE. in the relicensing and licensing review -

process and to provide' an . independent information base and computer programs to substantiate the technical basis for relicensing and licensing decisions in.HLW disposal.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED-FOR RESEARCH):

To modify the risk methodology developed for isolation of high-level radioactive waste in bedded salt so that it will be applicable to the analysis of HLW isolation in tuff.

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVE):

The transport of radionuclides in the vapor phase of water moving through unsaturated tuff does not appear to be significant.

• . Modeling work on the transport of radionuclides in unsaturated media requires experimental support.

A suitable computer program for simulating liquid water movement in a HLW repository in unsaturated welded tuff can be constructed by combining the

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best features of existing programs used in geothermal applications.

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3 B7121 FIN / TITLE: 87123/ CLIMATES OF THE HOLOCENE '

. CONTRACTOR: NATIONAL SCIENCE FND BUDGET: FY89 50K, FY90 50K,.  :

FY91 ~~EUK, FY92 - 5UK  !

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HLWM LEAD: FRED ROSS RES LCAD: R. KORNASIEWICZ

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HLWM NEED FOR RESEARCH (LIST):

%4-7nW4 - utis a-thercapability to assess the adequacy of DOE's prediction of climate changes and impacts of climatic changes on the hydrologic system.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

To provide information concerning the use of models to predict future climate changes and associate changes on site hydrology. This information will assist licensing staff is assessing validity of models and data used to predict  ;

future climates. '

n STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

Paleoclimatic data could be systematically evaluated to reconstruct

- coherent global paleoclimatologies at 3000 year increments back to 18,000 years B.C.

Climate simulation models can successfully simulate past climatic conclusions as derived from paleoclimatic data, at least en the coarse -

grid scale.  !

Climatic simulation models are now capable of investigating potential d future climatic conditions that might arise due to orbital changes, changes in the earth's albeoo or from anthropomorphic changes in the atmosphere such as increased 002 levels. )

Climatic simulation medels can be used to synthesize paleoclimate data {

to pt-oduce part climates in terms of global vegetative patterns which can  !

be used as temperature, rainfall and evapo-transpiration proxies to j estimate hydrologic regimes. 1 i

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SUMMARY

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' FIN / TITLE: ' Mb7/ kdh L T- 1I l CONTRACTOR: C. W kJ L4 BUDGET: FY89 K, FY90 K, FY91- K, FY92' K j J

<J HLWM LEAD: Te - *%

RES LEAD:

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HLWM NEED FOR RESEARCH (LIST):

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STATUS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):  !

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ENCLOSURE'2 o 8,.

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'HLWM RESEARCH SUtmARY FIN / TITLE 3 b 5 4 / N* dA5 l' T 9 kN f CONTRA'CTOR: CM W kk BUDGET: FY89 K, FY90 K,-

FY91 K, FY92 K

'HLWM LEAD: T, -

RES LEAD:

HLWM NEED FOR RESEARCH (LIST):

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

' STATUS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

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ENCLOSURE 2- .

p %mo. 1 p g 1 L ' HLWM _RESE/.RCH SUPMARY. -

FIN / TITLE: b I M/- A, M sws is

, CONTRACTOR: ha 87 BUDGET: 'FY89 K. FY90 K, i

FY91- K, FY92 K HLWM LEAD: T8 'O l- RES LEAD:

HLWM NEED FOR RESEARCH (LIST):

RESEARCH OBJECTIVES (LIST.:AND KEY TO HLWM NEED'FOR RESEARCH):

-STATUS OF RESEARCH TO D,LTE (LIST AND KEY TO RESEARCH OBJECTIVES):

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02505 FIN / TITLE:. 02505 /VAP20-VARIABLY SATURATED ANALYSIS MODEL CONTRACTOR:' HYDR 0 GEOLOGIC BUDGET: FYB9 K, FY90 105K, FY91 K, FY92 K HLWM LEAD: ROSS RES LEAD: NICHOLSON HLWM NEED FOR RESEARCH (LIST):

.This code was developed for modeling unsaturated flow and export problems j where there is a sharp wetting front moving. into a every dry soil (e.g., '

-low-level and mill tailongs waste)

RESEARCH OBJECTIVES-(LIST AND KEY TO FLWM NEED FOR RESEARCH):

.This code or numerical techniques may be transferable to pr,51s ems in HLW.

Tim McCartin.may use VAM 2D to model Apache Leap Problem.

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

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" ~ FIN / TITLE: D2012~/ ALLIGATOR RIVERS (FORMERLY " RADIONUCLIDES MIGRATION AROUND ORE BODIES...")-

CONTRACTOR: ANSI /NEA BUDGET:' FY89 180K, FY90 180K, FY91 K ,' FY92 K

.HLWM LEAD: . DAVID BROOKS

'RES LEADi ~ TIM McCARTIN HLWM NEED FOR RESEARCH (LIST):

l Provide guidance- to DOE (i.e., Extrapolation of Data T.P. and Radionuclides c Sorption T.P.)

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):-

~

I Data needs to model hydrology and migration of radioelement (U-234/U-238.Th230/U-234,Ra-226/Th-230) 3 Comparison'of field' and laboratory generated data (, }

STATUS / FINDINGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH'0BJECTIVES):

2 Uranium sorbed by amorphose iron'is directly accessible to groundwater.

and can be desorbed. Q

) Uranium sorbed by the(crystalline it-on phase is not accessible to groundwater and not likely to desorb.( z\

% . Over geologic time (TBD), uranium of th;e'amfrphous iron " migrates" to the crystalline iron and stay bound. 23 4 "The recoil effect," which result (s from the recoil of daughter .

i radionuclides in the process of alpha decay, leads to an accumulation of the daughter in the clay / quartz.

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l FIN / TITLE: M824 / VALLES CAULDERA CONTRACTOR: SANDIA BUDGET: FY89 200K, FY90 200K, FY91 TK, FY92 - TK 4 l

HLWM LEAD: B_RADBURY RES LEAD: K0VACH HLWM NEED FOR RESEARCH (ONE SENTENCE):

The uncertainties _ associated with the extrapolation of short-term laboratory results to long-term behavior expected in a HLW repository need to be determined.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEARCH):

1. To identify and characterize a natural analog of the hydrothermal alteration and transport of elements expected in a HLW repository in unsaturated tuff.

.2. To simulate in laboratory experiments the natural conditions and

~

processes that produce hydrothermal alteration'and transport of element.

'3. To compare the natural and experimental phase assemblages and determine the extent of the uncertainty associated with extrapolating short-term laboratory tests to long-term behavior.

4. To compare the results of geochemical and transport modeling with alteration assemblage-in the ffeld.

STATUS / FINDING OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):

1. Glassy tuff (Battleship Rock Tuff) at Valles Cauldera has undergone little alteration, preliminary conclusion is that water was driven off when the overlying Banco Bonito Obsidian was deposited, without water no alteration could occur.

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i FIN / TITLE: B6673/ GEOCHEMICAL ANALOGS CONTRACTOR: CWNRA BUDGET: FY89 285 K . FY90 450 K' FY91 500 K, FY92 0 K j

HLWM LEAD: 'BRADBURY l RES LEAD: MOVACH

.HLWM NEED FOR RESEARCH (LIST):

The uncertainties associated with the extrapolation of short-term laboratory; results, to long-tem behavior expected in a HLW repository need to be detemined. This contract.has not started yet but will fill the same need as .

A1824 which.is scheduled to end in FY90.

RESEARCH OBJECTIVES (LIST AND KEY TO HLWM NEED FOR RESEAPCH):

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Not known yet STATUS / FIN 3INGS OF RESEARCH TO DATE (LIST AND KEY TO RESEARCH OBJECTIVES):-

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ATTACHMENT 3 HYDROLOGIC-TRANSPORT SECTION RESEARCH NEEDS

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.H-T RESEAROi NEED i l

'Ibe Hydrologic Transport Section staff newk to have a description and an understardirg of rm- > riled surface ard subsurface methods to determine water j l

flux in unsaturated fractured rock media in climates similar to Yucx:a Mountain. )

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REASON FOR NEEDED RESEAROI i

1

- For an evaluation of a DOE Yucca Mountain performance demonstration the IGC needs to }mcu the accuracy of the calculated ground water flax through the proposed repository. 'Ihe rate (volume) of flux through the irmntain can have a

.large effect on radionuclides transport and ground water travel time evaluations

( mass and velocity), Wmm if characterization activities find thnt the Topopah Sprirgs natrix is close to saturation, a small increase in the flux through the welded units of Yucca Mountain will cause a significant increase in grourd water velocity (due to low matrix mv=ubility) . Therefore, it will be important to obtain an accurate determination of flux.

Etmc21CES 'ID NRC PROGRAM i

The NRC staff review of the SCP identified DOE plans to estimate flux frun surfa based studies in SCP Activities 8.3.1.2.2.1.2 and 8.3.1.2.2.1.3 and I

frun subcurface based studies in SCP Study 8.3.1.2.2.3. '

ASSOCIATED IEC RESEAROI i I

1

'Ibere is no NRC research on this need at this time. l I

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.iJ/ DOE RESEAR G G1 INVESTIGATIONS e

i-DOE plans to estimate flux frun surface had studies in SCP Activities -

. ~8.3.1.2.2.1.2 and 8.311.2.2.1.3 and fran subsurface had studies in SCP Study 8.3.1;2.2.3.

prepared by W.H. Ford (RES2) 6/05/89 10:30 f

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The Hydrologic Transport Section staff has a need for definite criteria to evaluate the appropriateness and accuracy of pneumatic tests (use of air or i i

gases) for detemining hydraulic parameters of water flow in the unsaturated j l

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REASOi FOR IE:EIED RESEAROI j i

2he Hydrologic Transport Section review of the SCP determined that pneumatic tests will be used to determine water flow paramters in several SCP activities, including Activity 8.3.1.2.2.3.2 (Site vertical bornhole studies),

Activity 8.3.1.2.2.4.1 (Intact-fracture test in the exploratory shaft facility), Activity 8.3.1.2.2.4.3 (bulk-permeability test in the exploratory shaft facility), Activity 8.3.1.2.2.4.4 (Radial borehole tests in the explorat:'y shaft facility), Activity 8.3.1.2.2.4.9 (Multipurpose-borehole testing near the exploratory shafts, and Activity 8.3.1.2.2.4.10 Hydrologic preparties of major faults encountered in main test level of the exploratory shaft facility). The NRC M to know the capability and accuracy of this technology, because of the large number of Irportant activities that will use this technology to obtain data for canpliance chiwLrution modeling, wKch the staff nust evaluate when it makes a canpliance determination.

o REFERENCES 70 NRC PROGRAM The NRC Irview of the DOE Site Omracterization Plan fourd in Activity 8.3.1.2.2.3.1 that preliminary prototype work is needed by DDE to develop ard evaluate various testing methods to ensure that matrix hydrologic property data

is useful, . Aq;susentative ard relevant to Wing flow and widte transport. One.of the methods for gd. stype evaluation will-be the use of pneumatic testing to determine water pamaahility, effective porosity, and a squ.uarnicative elementary volume (Activity 8.3.1.2.2.4.3).

ASSOCIATED NRC RESEARG NRC research is not investigating this topic at this time. However, the University of Arizona has coinv+M pneumatic tests in unsaturated fractured tuff similar.to Yucca Mountain as part of their investigations under FIN D1662,

" Unsaturated Flow, Ihase III", which as one of it's objectives, is to provide .  :

information on site characterization and modeling techniques for assessing an.

unsaturated zone site.

DOE RESEARCH OR INVESTIGATIONS DOE has plans as stated in the SCP (Activity 8.3.1.2.2.3.1, . page 8.3.1.2-189) that fluid pamaahility tests of air permeability, Klinkenberg air pamanhility -

at different overburden pressures, specific wate permeability, and oil pamaahility, Will be canpared. DOE acknowledges that "although water is the primary fluid of interest, air pamaahility is being evaluated because it it the quickest and least expensive method."

prepared by W.H. Ford (RES1) 6/05/89 15:00

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%a w ,,.n, (The' Hydrologic y Transport Section' staff has a need to understand h'o w to establish a representative elementary volume for flow'and transport in unsaturated, , ,

x fractured rocks.-

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"h Ig L ' REASON FOR NEEDED'RESEARCH

Oneof5theobjectivesof-YuccaMountainsitecharacterizationwillbeto L  : determine a.' representative elementary volume. below which discrete models of-

individual conduits must be u' sed to model flow and transport from the repository-and above which continum average properties of the hydrology can be used i.

f (Activity 8.3.1.2.4.3, Bulk-permeability test' in the- exploratory shaft

^ f acility) . This.is a very important concept for ground water modeling of Yucca Mountain becau'se it would greatly simplify the modeling process. The NRC needs

to evalua'te this the'ory, b' ecause it is a significant ground water modeling

• concept'.

REFERENCES TO NRC PROGRAM p

At this time it .is not practical to model unsaturated zone ground water flow and transport ~at the scale of the Yucca Mountain site by treating the fractures and matrix. separately. An alternative is suggested in the SCF that it is possible' y,,

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.to regard the matrix and fractures as separate but overlapping continuum systems 3 or as a' single composite continuum. These approaches assume that matrix'and fracture properties can be represented as spatial averages' over rock mass

' volumes, whose linear dimensions are very 'much smaller than the thickness of the hydrogeologic unit, but sufficiently large to include a representative,

!' statistical sample of hydraulically connected fractures.- The rock mass volume over.which the averaging is performed is' commonly designated-as a representative elementary volume. ;If a representative elementary volume can be established

' unsaturated ground water flow may be described as a single continuum composed of both matrix material and fractures. A ground water model using th.is. type.of representative elementary volume might represent'the dependence of relative

' hydraulic conductivity on liquid water potential in an unsaturated porous medium as shown.in Figure 3-34; where the combined curve represents how a block of unsaturated fractured rock would be modeled if a representative elementary -

i volume has been demonstrated. SCP Activity.8.3.1.2.2.4.2 (buik-permeability i test in the exploratory shaft facility, page 8.3.1.2-271)isdesignedto' determine a representative elementary volume for the Yucca Mountain site.

It is also possible that this representative elementary volume concept may be used in performance assessment modeling conducted as part of the Memorandum of Understanding between Research and the Division of Waste Nanagement.

ASSOCIATED NRC RESEARCH The NRC has not conducted any research of this topic.

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.- j lIn SCP Stucy' 8.3.1.2.2.4 (Characterization of Yucca Mountain percolation'in the unsaturated zone exploratory shaft facility study) it is stated that the innovative nature of determining an representative elementary volume' is

. recognized and prototype testing will be performed in support of Activity 8.3.1;2.4.3 '(Bulk-permeability test in the exploratory shaft facility) .which 7

will be used to. demonstrate the concept of an representative elementary volume for. Yucca Mt. (page 8.3.1.2-235). Prototyping testing will involve the I

Development of instrumentation, experimental te'chniques, technical procedures,

' ti and analysis. techniques.

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1 Prepared by W. Ford (RES3) 6/13/89 11:30 i.

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.RESS H-T RESEARCH NEED The Hydrologic Transport Section staff needs facts about flow and transport 1

prucesses and< knowledge about parameter measurement techniques to evaluate the current concepts of moisture characteristic relations for fracture / matrix flow in unsaturated fractured rocks.

REASON FOR NEEDr0 RESEARCH The Hydrologic Trans' port Section review of the SCP confirmed the observation that there is little data on unsaturated flow in fractured rock. However, several investigators have speculated on the behavior of flow in unsaturated fractures (Wang and Narasimhan, 1985; Klavetter and Peters, 1986; and Montazer andWilson,1986). These researchers model fracture conductivity as a function of fracture aperture distribution, fracture saturation, pressure head, and assune that the pressure heads in the fractures and the matrix are in equilibrium. This means that for flow to occur along the length of the fracture under unsaturated conditions, fracture aperture must be the same size or smaller than matrix pores where fluid flow is occurring. It also neans that if the fracture aperture is greater than the largest matrix pore size, flow will not occur along the length of the fracture until the matrix pores are almosc saturated. This hypothesis of frtcture/natrix flow, will be used to conduct performance assessment evaluations. This means that a fundamental premise of the flow / transport model has not been experimentally demonstrated.

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n g .The NRC' review of the DOE Site Characterization Plan found'that. Activity 8.3.1.2.2.4.fc has the objective of determining the hydrologic conditions that control the occurrence of. fluid flow within fractures and matrix.

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. ASSOCIATED NRC RESEARCH NRC research is not' investigating this topic at this time.

DOE RESEARCH OR INVESTIGATIONS f

'Prctetype testing at laboratory 'and field scales are planned prior to the exploratory shaft tests to confirm this concept of moisture characteristic relations for fracture / matrix flow in unsaturated media. Prototype tests are-g also planned,to develop the technology to conduct these tests -in the exploratory shaft. -. conceptual and numerical model development for fractured, porous

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unsaturated media will be a part-of the percolation test in the exploratory shaft' facility (Activity 8. 3 '.1. 2. 2 . 4. 2 ) . Further information on prototype D testing.is contained in Section 3.9.2.1 (page 3-171) of the SCP where it is.

stat'ed that'" Standard field and laboratory methods are not yet available by which to determine the moisture-characteristic relations for variably saturated t

fractures and fractured rocks. Prototype testing to develop such methods will

, .be conducted on welded tuffs from G-Tennel which are similar to those expected

'. ua to be encountered in the exploratory shaft facility. The benefits of this-

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" testing.are twofold:' first, the program will permit development of quality

. level 1 methods and procedures for ESF testing, and'second, the results of'the L . tests will provide preliminary data regarding the hydrologic behavior of.

fractured welded tuff. - Thus, preliminary assessment of the appropriateness' of the models of f'ow processes will be possible."

Activity 8.3.1.2.2.4.2 will test the water flow and chemical transport

-properties of the Topopah Spring welded tuff at the repository horizon to resolve the contributions of fracture and matrix flow bnder varying artificial percolation rates. This test will try to define conditions for the-initiation 1

of significant fracture flow and the propagation of percolation pulses via fracture.

-REFERECES CITED 1.laveter and Peters,1986, " Estimation of Hydrologic Properties for an Unsaturated, Fractured Rock Mass," SAND 84-2642, Sandia National Laboratories, Albuquerque,,NM.

Montazer, P. and W.E. Wilson,1984, " Conceptual Hydrologic Model of Flow in the Unsaturated Zone, Yucca Mountain, Nevada," Water-Resources Investigations Report 84-4343, U.S. Geological Survey, Denver, CO. I 1

1 . .

RESS Peters, R.R., l'988, "Kydrologic Technical correspondence in Support of the Site Characterization Plan", SAND 88-2784, Sandia National Laboratories, Albuquerque, NM.

A Wang, d.S.Y. and.T.N. Narasimhan,1985, " Hydrologic Mechanisms governing Fluid Flow in Partially Saturated, Fractured, Porous Tuff at: Yucca Mountain,'.'

SAND 84-7202, Sandia National Laboratories, Albuquerque, NM. l prepared by W.H. Ford (RES5) 6/05/89 14:00 I

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' j i i i i DECREASING LOG MATRIC POTENTIAL 4 h INCREASING LIOUlD-V1.0 dR SATURATION Figure 3-34. Idealized hydraulic-conductivity characteristic curve for a composite (fracture-matrix) porous medium. Modified from Montarer and Wilson (1984).

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1. HYDROLOGIC TRAF1 PORT RESEARCH NEED Hydrologic transport staff needs an appraisal of a method of determining water composition in unsaturated rocks based on the equilibration of zeolites with aqueous phase components and isotopes.

2. Reason for Needed Research Current methods of extracting' water from the matrix of rocks from the unsaturated zone for determining groundwater .

compositions are still in the developmental stage (Yang, 1986). These methods include compression, centrifugation, and vacuum distillation of the rocks. Compositions of the pare watern depend on the methrq of extraction. Thus, for a given rock from the unsaturated none, the measurement of a unique pore water composition is not yet attainable, j I

Zeolites are unique aluminosilicate minerals because of i their ability to rapidly equilibrate with groundwater at low )

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temperatures. If the thermodynamic constants and isotopic l 1

fractionation factors for the exchange reactions involving cenlites and components in the aqueous phase were known, it j would be possible to calculate groundwater composi tions f rom neolite compositions. The potential advantage of this )

method over the prasent methods is the relative ease of 1 I

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sampling zeolites. Furthermore, cince neolites are expected to provide the bulk of the sorption capacity of the tuff, knowledge of ion exchange properties is required for accurately modeling transport at the HLW site. The hydrologic transport staff could utilize the neolite composition method to verify the compositions of ground water in the unsaturated zone determined by DOE and their contractors.

3. Reference to NRC Programs This research is needed for developing the technical position entitled " Chemical Interactions in Unsaturated Fractured Rock." The current approach used by DOE to model chemical . interactions in the unsaturated zone is to assume l I

that the chemistry is identical to that in the saturated  !

one. The staff proposes to determine the limitations of 1 k

1 this assumption and develop criteria concerning the modeling {

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of transport processes in the unsaturated zune, j l

This research would also provide information for the  !

NRC HL.W technical review staff for evaluating the following Study Plans:

I R.'.1.2.2.7 Hydrochemical character 1:ation of the i

unsaturated zone

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9.3.1.2.2.9 Site unsaturated-zone modeling, synthesis,' and integration. j 1

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4. Associated NRC Research j

.The CNWRA has committed to study the application of cryo-electron microscopy and x-ray microanalysis to geochemical' characterization of pore waters under Activity 2.2.1.1. of the Geochemistry Project Plan as described.in the letter of J. E. ((a t z to M. Mace on January 13,-1988.

5. Associated DOE Research or Investigations The USGS au contractor to the DOE is studying the feasibilit.y of extracting water from rocks from the unsaturated zone by applying pressure. The compositions of the extracted waters are determined using conventional techniques. See DOE studies referenced in Item 3.

Reference Yang, A., 1986, Summarv of Proaress Report, Unsaturated Zang Hydrochemistrvt February 12, 1986, U. S. Geological Survey.

prepared by J. W. Bradbury 6-8-89

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I HYDROLDGIC TRANSPORT RESEARCH NEED l

The Hydrologic Transport Section staff needs to know the minimum acceptable testing program to test the hypothesis that flow through fractures and faults in nonwelded tuff (i. e., the Calico Hills nonwelded unit) is negligible.

REASON FOR NEEDED RESEARCH

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I The Hydrologic Transport Section staff has to determine the acceptability of i

the testing program, to be developed and implemented by DOE, to test the hypothesis that flow through fractures and faults through the Calico Hills nonwelded unit is negligible. This hypothesis is the fundamental basis for both designating the Calico Hills unit as the primary barrier of the geologic setting and assuming that calculation of groundwater travel time and release of radionuclides to the accessible environment using an equivalent porous media approach (in nonwelded tuff units) is appropriate.

REFERENCES TO NRC PROGR/d!

l The NRC staff review of the Site Characterization Plan for the Yucca Mountain Project found.that proposed plans to characterize the geohydrologic properties of the Calico Hills (a nonwelded tuff unit underlying the repository horizon at Yucca Mountain) are limited. Characterization of the unit is limited due to a concern that penetration of the Calico Hills unit within the repository block may affect the performance of the site.

ASSOCIATED NRC RESEARCH

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- NRC'research'is not'directly investigating this topic at this time. However, past research in unsaturated, fractured rock done by the University of Arizona may. contribute bo developing the criteria by which a minimum acceptable testing

' program is. determined'for standards that the licensing staff could apply to the future testing plan review.

DOE RESEARCH OR. INVESTIGATIONS i DOE a current plans for characterizing the Calico Hilla unit are limited to surface-based studies (vertical boreholes). It is acknowledged in the SCP that the.'aurface-based studies will provide very limited information about the t, ,

distributions'and flow characteristics of fractures and faults in the Calico '

Hilla and thus, are of limited use in supporting the hypothneia of negligible.

i flow through faulta and fractures. Development of in situ testing in the Calico Hilla na part o'f an exploratory shaft facility is'in abeyance because of

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a concern that penetration of the unit within the repository block may affect j the performance of the site. Alternative approaches (shaft sinking and-

~ drifting in the vicinity of the site and various combinations of vertical and angle drillholes and excavation) are being conaidered. Potential trade-offa

- between the need to acquire data and the need to preserve site-performance  ;

capabi'11ty are being evaluated by DOE with a rish-benefit analysis. Selection at appropriate test options will be made, and consultations with NRC staff .

held, prior to initiating testing.

Prepared by J. Pohle, 6/18/89 l

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at l HYDRULOGIC TRANSPORT RESEARCH NEED  ;

lhe'H-T staff needs a. review of-methods to analyze groundwater flow'  ;

- i systems based on hydrochemical data. The hydrochemical. data would j g '- 1 include anthropogenic contaminants known as " bomb pulse" radioisotopes, such.

l' as tritium, technetium-99, iodine-129, chlorine-36, and others. .A specific  ;

need.is for methods to interpret hydrochemical date from fractured rock l regimes under phreatic conditions where the water table occurs beneath a

' thick'uadose, zone. Phenomena to be interpreted include recharge and

-groundwater. travel times. An integral part of the general need would be recommendatiotr for appropriate methods to determine regional background

! i- levels of radioisotopes in groundwater, along with a listing and critique of p;

methods for collecting uncontaminated hydrochemical samples from both the y

saturated.and vadose' zones.

REASON FOR NEEDED RESEARCH

.The H-T. staff needs comprehensive understanding and review criteria for hydrochemical methods, used in the analysis of groundwater flow systems, to make informed reviews of DDE data collection activities and better evaluate DOE's data interpretations. Such analyses may contribute to

' empirical estimates of seepage velocities in the vadose zone.

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.. e Hydrochemica1'interpreti 3ns may independently validate site flow and transport modeling. S t'a . needs better understanding of the hydrochemical _

!' methods for model validation, and if' appropriate, may use-such methods .

1  !

'in-the staff's independent NOU site performance assessment exercise.

Information on appropriate methods to determine groundwater background levels i of radioisotopes in the Yucca Mt. ~ region is needed to judge the ' quality of data obtained by planned DOE site characterization activities. Determinations of natural background levels are important for assessing whether radioisotopes observed at depth in site wells are of naturel or anthrspoganic origin.

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As determined in the SCP review, DOE is developing water sampling techniques '

for the unsaturated zone in a prototype development program. Techniques for

. i collecting uncontaminated hydrochemical samples are important to provide  ;

high quality data and reliable hydrogeologi' interpretations. NRC's independent knowledge of sampling techniques is needed to conduct informed .

j reviews of DOE's hydrochemical data collection activities.

REFERENCE TO NRC PROGRAMS This need for Yucca Mt. became apparent during the SCP review.

Comment SCP/ YUCCA /NMC/COM/9 stated that, consistent with Regulatory Guide 4.17, at sites where human activity may have introduced radioactivity to the ground water, analysis should be done for those radioisotopes that are.

known or suspected to have been added to the system. Iodine-129 and L- _ - _ -

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technetium-99 were not included by- DOE in the group of radioisotopes to.be analyzed from water samples collected'at the water table and from any perched zones. .These radioisotopes are among those identified in Appendix A of.the EPA release standards. The background levels and variability of these radioisotopes in saturated zones should be assessed as part of site characterization to provide baseline information for a performance confirmation program at Yucca Mt.

ASSOCIATED NRC RESEARCH There is no ongoing NRC research that directly addresses this research need.

ASSOCIATED DOE RESEARCH OR INVESTIGATIONS 0.3.1.2.2.2 Study: Water movement tracer tests using chloride and Cl-36 measurements of percolation at Yucca Mt. (Tc-99 also discussed

. under this study) l' L

8.3.1.2.2.7 Study Hydrochemical characterization of s unsaturated zone 8.3.1.2.3.2 Study Characterization of the saturated zone hydrochemistry DOE's principal emphasis is to use hydrochemistry to help assess recharge.

For example, the objective of activity B.3.1.2.2.2.1 is to quantify the amount of percolation flom precipitation into the unsaturated zone. One of the

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W objectives of study 8.3.1.2.2.7 is to provide independent evidence of flow I direction, flux, and travel time of water in the unsaturated zone. An objective of activity 8.3.1.2.3.2 is to aid in the identification and l quantification of fluxes to, from, and within the saturated zone.  !

No plans were found in the SCP for the investigation of regional background

-levels of radioisotopes that are relevar.t to repository performance. These radioisopes include, 1 hose listed in the EPA HLW release standards. ,

i i

One of the objectives of Activity ~ 3.1.2.2.7.2 (aqueous phase chemical 3 investigations) is to design and implement methods for extracting pore fluids from unsaturated zone tuff units. As stated on SCP page 0.3.1.2-338, various -l 1

methods will be evaluated during prototype testing.  ;

t PREPARED BY: NEIL M. COLEMAN, 6/21/89 l

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