ML19309F810

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Submits Trip Rept Re 781212-15 Visit to DOE Albuquerque,Los Alamos & Rocky Flats Ofcs.Purpose of Trip Was to Gather First Hand Info for Waste Mgt Licensing Study.Doe Organizational Charts & Memos Encl
ML19309F810
Person / Time
Issue date: 01/08/1979
From: Rich Smith
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Cunningham R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML19309F811 List:
References
RTR-NUREG-0527, RTR-NUREG-527 NUDOCS 8005010325
Download: ML19309F810 (17)


Text

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MEMORANDUM FOR: Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety FROM:

R. Dale Smith, Chief Operations and Planning Branch

SUBJECT:

TRIP REPORT, VISIT TO ALBUQUERQUE, LOS ALAMOS, AND ROCKY FLATS, DECEMBER 12 - 15, 1978 In order to gather first hand information for the Waste Management Licensing Study, NRC staff visited the Albuquerque Operations Office t

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of the Department of Energy and operations at Los Alamos and Rocky Fl a ts.

Participating in the visits were R. E. Cunningham, R. D. Smith, D. K. Rathbun, J. Axelrad, and D. B. Matthews.

December 12, 1978 The NRC contingent presented a briefing to DOE representatives.

The DOE personnel had been gathered from all of the DOE Operations Offices and consisted of senior management with responsibilities in national security progr4ms and environment, health, and safety. We outlined the scope of the Congressionally mandated study and discussed the regulatory options under consideration.

The NRC staff also outlined our needs for information related to waste activities and inventories.

l At the conclusion of the two hour briefing, the NRC staff was excused and the DOE staf f continued with their deliberations.

The remainder of the day was spent in discussions with senior staff members from the Operational Safety Division and the Waste Management B ranch.

The Waste Management Branch is a part of the Weapons Production Dtvision, under the Assistant Manager for Operations (see attached organizational charts). The Branch is responsible for performing site appraisals of waste management activities, monitoring operations to assure proper quality assurance is provided and that appropriate Federal regulations

l Richard E. Cunningham.-

(e.g., EPA) are being met. The branch is also responsible for participating in the SWIMS program, which is an integrated computer based information system that is developing a complete inventory 0" all solid waste in DOE disposal sites.

We were furnished with DOE's recently israd INITIAL DISPOSAL CRITERIA FOR DOE SOLID LOW-LEVEL WASTE (copy attached).

The Weste Management Branch consists of a Branch Chief, Secretary, and three professional staff members.

December 13, 1978 The NRC staff was briefed by members of the staff of the Operational Safety Division.

In particular, tlie organization and functions of the Health Protection Branch and the Facility Design and Safety Analysis Branch were discussed in detail (see attached organization chart).

The safety review of a proposed project begins during the conceptual stage when an engineer from the Facility Design and Safety Analysis Branch is assigned to work with the team designing the new project.

Their safety review function continues throughout the life of the project.

from the design phase through the construction and finally to the initial operations.

It is their opini'on that this allows them to be much more familiar with the project and to exert their influence at the most effective time, i.e., during the design of the facility.

The FD3A Branch give the NRC staff complete access to their files of safety analysis reports and evaluations. Specific examples were chosen for further review by the NRC task force staff.

The FDSA Branch consists of the Branch Chief, Secretary, and four professional staff members.

The Health Protection Branch has broad responsibilities in the areas of health physics, industrial hygiene, occupational medicine, industrial safety, and environmental assessment. Because of these many responsibilities and the wide variety of programs to which they are applied, the management of radioactive wastes is a relatively small part of their activities.

The Health Protection Branch consists of a Branch Chief, Secretary, and six professional staff members.

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Richard E. Cunningham.-

During the t. o days, considerable information about waste disposal and storaga :ctivities was acquired and is summarized in the attach-ments to this memo.

Principal DOE Staff contacted were:

Thomas R, Clark, Deputy Manager, ALO Jack P. Roeder, Director, Operational Safety Division Willis B. Johnston, Deputy Director, Operational Safety Division Ray L. Miller, Chief, Health Protection Branch William B. Sayer, Chief, Facility Design and Safety Analysis Branch Robert Y. Lowrey, Chief, Waste Management Branch Thomas H. Bosworth, Waste Management Branch A. L. Martello, Waste Management Branch December 14, 1978 R. D. Smith and D. B. Matthews visited Los Alamos to inspect several waste activities to obtain a better understanding of their operations.

Liquid waste treatment - The LASL facilities for the treatment of contaminated liquid effluents were visited. There are two such facilities,

  • one of which processes wastes contaminated with transuranic elements.

Both systems operate on the same principle, which is a standard water treatment process in which contaminants are removed by a ferric hydroxide flocculant that is filtered and disposed of.

For the TRU waste, the precipitate is mixed with concrete and disposed of in galvanized

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iron pipes set into the ground (see attached report, Review of Radioactive Liquid Waste Management at Los Alamos, and LASL mini-review LASL 78-83 l

for further details).

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Solid waste treatment - NRC staff toured the TRU solid waste treatment development facility. This facility is undergoing final tests before becoming operational with TRU waste. The principal feature of this facility is an incir.erator for the volume reduction of TRU waste.

The two chambered incinerator burns the wastes under controlled air input to minimize particulate production and to assure complete comb"stion (see attached LASL mini-review, LASL 78-83 for further descriptf or?

Solid waste storage and disposal - NRC staff visited the low-level waste disposal site G to observe operations. The sh; land burial 4..

of laboratory wastes that do not contain TRU takes place in trenches i

dug into the light, dry, volcanic tuff that underlies the LASL site.

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Richard E. Cunningham Retrievable storage of TRU waste is also carried out at this site.

using trenches dug into the tuff formation (see attached LASL mini-review, LASL 78-5, for further description).

Principal LASL staff contacted were:

Lamar JC'nson, H Division Thomas K. Keenan, Group Leader, A-7, Waste Management Dale Thompson, Waste Management John L. Warren, Waste Management December 15, 1978 R. D. Smith visited the Rocky Flats Plant and the Rocky Flats Area Office to obtain information about waste activities at the site.

Information relative to on site storage and disposal is incorporated in the summary attached to this memo.

Rocky Flats contains some early day disposals and burials of contaminated soils and sewer sludges. There is one burial of 25,000 kg of depleted uranium metal on site. According to officials, all of this will be decontaminated and/or removed in time.

(See attachment for location of waste disposals and storage)

Rocky Flats is the " lead contractor" for the DOE program to treat and dispose of TRU wastes. A briefing on several aspects of this program was presented. A major activity in the near future will be the slagging pyrolysis treatment of stored TRU waste at INEL.

This facility will convert the waste into a glass-like slag which will greatly reduce the volume and render the waste into a stable form for ultimate disposal.

The facility is targeted for FY 86 startup at a cost of about $500 million.

An on-site visit was made to the new facilities for treatment of TRU contaminated liquid wastes. This sytem is similar in principle to the LASL system, but is orders of magnitude larger. The entire system is reported to be built to standards comparable to NRC requirements.

It is a totally contained series of receiving tanks, precipitators, l

filters, evaporators, and spray driers. The filtered flocculant is sent to INEL for storage as TRU waste.

Nitrate salts with very minor Pu contamination are sent to Nevada Test Site for disposal.

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Richard E. Cunningham,

In addition, the Rocky Flats fluidized bed TRU waste incinerator was visited. This pilot plant installation is intended to reduce the volume of combustible waste through combustion, while at the same time preventing the escape of particulates and dangerous gases and combustion products.

Facilities for the preparation of solid TRU waste were toured.

Extensive prepackaging operations are carried out by workers in supplied air suits. Oversized items are cut up, waste is sorted, and placed into shipping containers under these difficult working conditions. The containers are staged and prepared for shipment in a large warehouse on site. Shipments are made in specially designed rail cars, designated as ATMX cars.

Principal staff contacted:

Earl Beam, DOE, RFA0 Gary Echart, DOE, RFA0 Bill Bennett, Rockwell Bert Kelchner, Rockwell WA.

R. Dale Smith, Chief Operations and Planning Branch

Enclosures:

As stated l

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le/w/~9 UNITED STATES DEPARIMENT OF Ef4ERGY ALBUQUERQUE OPER AT10HS April, IMS 371/374 PROJECi OFFICE -

0FFICE OF THE MAN AGER CONTR ACT COMPLlAtiCE OFFICE Harry F. Mumma H eem an E. Ro ser. Manage, Joe C. Gaecio Thomas R. Cla,k Deg.,ey M an ag e, I

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W.ll.ua R. Cooper, As st. Mg<.

John F. Buebe. As se. Mge.

Hugh D. Leenhoues, Asse. p e.

g Chief Counsel OF FICE OF CL A551F. AND TECH.

OPER ATION AL 5AFETY CONTRACTS *FD AUDI T & APP R A15 AL lHFORM ATION Dtvis!ON BUDGET DivislON Otvis10N

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Chief, C. A. Durch Chlef. R. L. Miller Chief, W. D. Sayer Chief, K. E. Elliott Chief, D.' L. Foster Chief, R. M. Shay FIrc Prclection and llealth Phystcs Preliminary Proposals Nuclear Criticality Safety Operational and Hattonal Sarcey studies of all Pr eventio*

Environmental Pollution, Cor.ceptual Design Review Reactor and Critical Mass Eincegency Planning IJ T5 Events lidustrial Saf ett Control 8. Assessment Desica Criterla Review Laboratory Safety Radiolor.ical Assistance DOD Weapons Systems Transpretation Safett Occupational Medicine Title i Review Fissile 1.taterial, We.* pons P'ogr ani Salcty Stin?n s linlilal Es;rlosive $ately inttustrial flygiene Title il Review "P'

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G. W. JOHNSON T'.'*H. B O S W O RT H A. L. M ARTELLO

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TRU PROGRAM MANAGER SITE APPL 1AISALS HAZARD 0US MATERIALS [ EPA) 6a MEMBER Of WACSC OPERATIONS FEDERAL REGULATIONS QUALITY ASSURANCE SITE PLANS

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TRANSPORTATION SWIMS LLW/0&D/ AIRBORNE APPRAISAL SUPPORT h'

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NOV 15 1978 Department of Energy Washington, D.C. 20545 T0:

'H. E. Roser, Manager, Albuquerque Operations Office R. H. Bauer, Manager, Chicago Operations Office C. E. Williams, Manager, Idaho Operations Office M. E. Gates, Manager, Nevada Operations Office R. J. Hart, Manager, Oak Ridge Operations Office A. G. Fremling, Manager, Richland Operations Office J. B. LaGrone, Manager, San Francisco Operations Office N. Stetson, Manager, Savannah River Operations Office FROM:

Sheldon Meyers, Program Director o

Office of Nuclear Waste Management /Agg

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SUBJECT:

INITIAL DISPOSAL CRITERIA FOR DOE SOLID LOW-LEVEL WASTE There presently does not exist either national or DOE wide criteria applicable to the disposal of solid low-level waste. The Nuclear Regulatory Commission (NRC) is in the process of developing such criteria, hcwever, NRC docs not plan to promulgate icw-level waste criteria for several years.

Therefore, since January 1978 a joint headquarters / field effort has been undenfay to develop criteria for the disposal of DOE solid low-level waste. This effort has resulted in the attached initial disposal criteria which you should implement forthwith. The criteria are stated in general terms to minimize disruptions to operations and to maximize field flexibility.

During FY 1979, operating contractors should be required to develop implementing procedures.

These procedures should be reviewed and approved by the appropriate field office. At the end of FY 1979, the status of this effort will be reviewed for progress and modification as necessary.

As lead field office for our low-level waste program, ID will be in con-tact with each field office during FY 1979 to review the plans and progress toward implementing these initial criteria. The need in FY 1979 and FY 1980 is to develop the basis for final criteria which are specific and quantified to the maximum extent.

Various projects are now undenvay which are. designed to produce an adequate scientific data base for the development of final disposal criteria in FY 1980.

It is expected that operations under the attached initial criteria will provide an operating experience data base which will provide cost / benefit information for the development of the final criteria.

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MULTIPLE ADDRESSEES 2

Disposal of low-level radioactive waste is of concern to both DOE and the public. By making DOE's opera,tions more systematic and formalized, we can better demonstrate to the public that this activity can be undertaken in a safe, environmentally sound and economical manner.

Attachment:

Initial Disposal Criteria for DOE Solid LLW s

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Initial Disposal Criteria

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DOE Solid low-Level llaste Purpose The' purpose of these criteria is to provide that DOE solid low-level waste (LLW) is disposed of (1) in a safe and economical manner, (2) with an acceptable environmental impact, (3) with minimum reliance on long-term surveillance and/or maintenance activities, (4) with acceptable risk to future generations, and (5) with minimum land usage.

It is rec'ognized that the general and preliminary nature of these initial criteria will lead to substantive changes in order to provide system-wide, quantified final criteria in FY 1980.

Goals Disposal site operations should:

1.

Encourage minimum waste generation and minimum land usage by applying good housekeeping practices, volume-reduction techniques, better land-fill designs and improved disposal methods consistent with operational, health and safety requirements.

2.

Use disposal methods and waste conditioning techniques which minimize long-term environmental impact, dependence upon long-term surveillance-and/or maintenance, and potential risks to future generations.

3.

Generate a properly recorded operating experience data base reflecting i

environmental and health and safety results of the disposal method (s)

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in use.

4.

Operate, and interpret results of existing and improved site perform-ance surveillance system (s) to assist in the evaluation of the' performance of the disposal site and practices.

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General I

.a. Good housekeeping and industrial operating practices shall be employed.

b.

Occupational health and safety, environmental and security i

standard; shall be met in all operations.

c.

Land usage for disposal shall b.

minimized without compromising ~

health and safety.

d.

Emergency response systems should be tested routinely.

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e.

Technology should be assessed periodically to upgrade practices (volume reduction, containment, surveillance).

f.

Plans shall be made for the long-term control and ultimate dis-position of the site using the latest technical and land use information.

g.

A quality assurance program shall be maintained.

e-II. Administrative a.

An individual responsible for all disposal site operations shall 1

be specified. The responsibilities and authorities shall be documented and shall include (but not be limited to):

(1) Documenting chmpliance with appropriate directive's, standards and procedures.

(2) Developing and implementing standard operating procedures.

(3) Establishing waste acceptance criteria and, where appropriate, determining the acceptability of input waste.

i (4) Providing estimates of resources necessary to assure that site and operations meet standards.

(5) Providing waste volume projections.

b.

Generators shall be encouraged to minimize waste generation.

Con-

. j9 sideration should be given to charging a portion of disposal costs to the generator, such as a sliding charge scale that discourages generation.

c.

An independent review system shal.1 be established.

d.

Anomalous occurrences at the waste disposaT area shall be reviewed

'and analyzed, and corrective measures implemented and documented as required.

III. Site Selection a.

The site shall.have suitable geological, hydrological and clima-tological properties which are tested, documented, reviewed and accepted by competent authorities to avoid excessive dose to man from radioactive and nonradioactive contaminants.

b.

Impact on ecological and archaeological conditions shall be minimized.

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3-c.

Transportation of waste, population distribution, and availability of utilities and other site support factors should be. considered.

d.

Recognized potential uses should be considered for an area prior to its being dedicated for waste disposal so as to minimize the

' impact of land withdrawal.

IV. Site Ooeration a.

Approved standard operating procedures shall be centrally docu*

mented, implemented, reviewed annually and revised as necessary.

_. Procedures shall include:

(1) Waste acceptance' requirements including contents and labeling (2) Disposal method and location (3) Criticality, radiation and occupational safety (4) Method of handling unacceptable waste or packaging

(.5) Proper handling equipment and technique's to be used (6) Decontamination of personnel, vehicles, equipment and l

facilities i

(7) Fire prevention methods i

(8) Segregation of TRL waste for retrievable storage (9)

Emergency response plans (10) Consideration of potential future discovery of artifacts.

(11) Quality asst 7ce program (12) Site surveillance program b.

Methods should be established to control:

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(1) Wind dispersion of waste or contamination (2) Water intrusion (3) Dust (4) Chemical hazards

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(5) Vehicle and personnel traffic (6) Materials with the potential of mobilizing waste (solvents,

. organics,etc.)

(7) Intrusion by vegetation or animals Specifications for containment designs and construction shall be c.

developed and implemented for all packaging and disposal techni, ques.

d.

Measurement methods will be implemented, documented and updated as appropriate for:

(1) Radiological conditions in and around the disposal area' (2) Migration of contaminants (radioactive and nonradioactive) in surface and ground water Uptake of ra'dionuclides by vegetation and animals (3)

(4) Release of airborne contaminants Exposures to site operating personnel and off-site population e.

shall be kept as low as practicable.

V.

Site Maintenance Adequate site ~ drainage systems shall be maintained.

a.

b.

Final cover shall be maintained to control surface accumulation of water.

Adequate erosion control measures shall be employed.

c.

d.

Corrective action shall be taken when maximum authorized levels of radiation are approached or predicted to occur.

A method to identify the location of disposed waste shall be e.

maintained.

f.

Conceptual hydrological model shall be developed utilizing local geohydrological and radi.ological data, and surveillance systems shall be maintained to aid in detecting and evaluating s.ubsurface migration.

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.c 5-VI. Support a.

Adequate fire suppression shall be available.

b.

Security shall be adequate to preveilt unaut or zed access to h i waste.

c.

Operators shall be qualified for their du :ies, and an adequate training program should be implemented.

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d.

Permanent records shall be maintained on:

(1) Waste volume, content, properties and location (2) Interpreted results of surveillance and monitoring programs l

(3) Routine and significant nonroutine events (4) Results of periodic independent evaluation of operations (5) Results of emergency response tests (6) Site geological, hydrological and climatological properties (7) Operating personnel and dose accumulation 6

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Summary

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Information Received from Albuquerque Operations Office Personnel During NRC Site Visit LASL 13 official waste locations (some TRU storage, some LLW disposal) two are active (G and T) two additional areas (H and Y) which appear to be contaminated no new burial grounds planned; G can be expanded a TRU waste teeatment facility Will start operating in 1979.

This is a R&D facility which can be used for backlog of waste or waste as generated.

no treatment activities currently Pantex one trench and 16 cylinders for LLW and TRU waste i

trench is inactive no treatment activities currently or planned no new waste locations planned SLA LLW disposed of in technical areas II and III area II is inactive; area III is active i

no storage or treatment currently or planned Rocky Flats site has a number of past burial locations no storage or treatment currently or planned

Volume in ft - Cumulative FY 1978 i

TRU Non-TRU Total i

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Stored Burial I

LASL 68,767 580,085 5,131,263 9,058,687 U,FP,H 3,278,572 8,409,835 l

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60 48,327 48,387 Pantex 38 1,143 4,553 5,734 I

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