ML19323C299
| ML19323C299 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 01/31/1980 |
| From: | Rich Smith, Wodrich D EMVROCIE, ROCKWELL INTERNATIONAL CORP. |
| To: | |
| Shared Package | |
| ML19323C296 | List: |
| References | |
| RHO-CD-882, NUDOCS 8005150302 | |
| Download: ML19323C299 (63) | |
Text
80051503o1 RHO-CD-882
. D
- nspection And Eva;uation Of Nuclear Fuel Services High
- _evel Waste Storage Systen*
3 5
Program Plan i I
January 1980 Prepared for the U. S. Nuclear Regulatory Cammisslan Under U. S. Department of Energy Contract DE AC06 7701030 l
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Rockwell intemational s Reckwell Han* crc Ccer1tions Energy Sy: tem. Group
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RHO-CD-882 eua......a,..
January 1980 **""**
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Rockwell Hanford Operations Richland, WA 99352 TIT b g amo au TM..
INSPECTION AND EVALUATION OF NUCLEAR FUEL SERVICES HIGH-LEVEL WASTE STORAGE SYSTEM PROGRAM PLAN WASTE TECHNOLOGY PROGRAM OFFICE PROGRAM BUSINESS MANAGEMENT RESEARCH AND ENGINEERING i otsTRisuTtON esaws s ut LDies e a ta es aws suskosme a.Ka U. S. Nuclear Regulatory Comission Rockwell Hanford Operations Office Director NMSS H. Babad A. T. Clark, Jr. S. S. Bath C. J. Haughney - 25 G. A. Beitel L. C. Rouse R. K. Brazeal L. C. Brown Nuclear Fuel Services, Inc. J. S. Buckingham J. P. Duckworth - 3 D. B. Car W il W. H. Lewis D. J. Cockeram A.
Pierce D. J. Flesher R. S. Gruhn New York State Energy Office stasgn ng T. K. DeBoer - 3 M. K. Harmon H. H. Hopkins, Jr. I U. S. Denartment of Enercy Headouarters J. E. Kaser l R. W. Barber B. E. Knight D. McGoff E. J. Msiancic J- Turi G. N. Langlois j H. B. Lindberg l P. F. Mercier i
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Rockwell Hanford Operations Richland, WA 99352 TITLE amo auTMom INSPECTION AND EVALUATION OF NUCLEAR FUEL SERVICES HIGH-LEVEL WASTE STORAGE SYSTEM PROGRAM PLAN WASTE TECHNOLOGY PROGRAM OFFICE PROGRAM BUSINESS MANAGEFINT RESEARCH AND ENGINEERING 6 OIST RIB U TIO N waut By:LOINe ansa NAME Buabo8M6 AREA Rockwell Hanford Operations (Cont.) U. S. Department of Eneroy -
W. E. Nees Ricnland Ooerations Office R. G. Oliver P. A. Craig G. G. Pitts C. J. Elgert R. Rapheal P. G. Harris R. C. Real M. W. Shupe J. H. Roecker F. R. Standerfer l R. C. Routson !
R. E. Smith U. S. Department of Enerqy-H. C. Spanheimer Savannan River Ooerations Office R. J. Thompson
- i. B. Veneziano E. S. Golberg
- a
', y kog Savannah River Laboratories D. D. Wodrich .R. A. Garvin Document Control (2) D. A. Orth J. A. Porter I
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I INSPECTION AMD EVALUATION OF NUCLEAR FUEL SERVICES HIGH-LEVEL WASTE STORAGE SYSTEM PROGRAM PLAN l
A- .
Submitted by: / / .
Date A/ //IB C E. Smith, Pfodect Manager, "
~
i Comercial Waste and Spent Fuel I i
Approved by: D3 d4.) Date3llLlPo D. D. Wodrich, Program Director Waste Technology Approved by: Date U.S. Nuclear Regulatory Comission Rockwell International Rockwell Hanford Operations Energy Systems Group
, Richland, Washington
o L, y .
4 RHO-CD-382 CONTENTS I. I ntroduc ti on . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 A. B ack gro u n d . . . . . . . . . . . . . . . . . . . . . . . . 1-1 B. N eed . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 C. Summary . . . . . . . . . . . . . . . . . . . . . . . . . 1-3
~
II. O bj ec ti ve s . . . . . . . . . . ~. .' . . . . . . . . . . . . . . 2-1 III. Scope ............................3-1 _. .
IV. Program Description .....................4-1 A. Bases . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1
- 8. Ass ump ti on . . . . . . . . . . . . . . . . . . . . . '. . . 4-1 C. Work Breakdown S tructure . . . . . . . . . . . . . . . . . 4-2 D. Narrative . . . . . . . . . . . . . . . . . . . . . . . . 4-5 Program Management and Support . . . . . . . . . . . . . 4-5 T ank .and V au l t I ns pecti on. . . . . . . . . . . . . . . . 4-7 Soil Transport Studies . . . . . . . . . . . . . . . . . 4-14 Thermal Evaluation . . . . . . . . . . . . . . . . . . . 4-18 V. Program Schedule . . . . . . . . . . . . . . . . . . . . . . . 5-1 VI. Resource Requirements . . . . . . . . . . . . . . . . . . . . 6-1 Tables: l
, VI-1 Budget Sunmary by Activities . . . . . . . . . . . 6-2 VI-2 Resource Requirements by Cost Elements . . . . . . 6-3 VI-3 Program Management and Support . . . . . . . . . . 6-4 VI-4 . Tank and Vault Inspection. . . . . . . . . . . . 6-5 VI-5 Soil Transport Studies . . . . . . . . . . . . . . 6-6 VI-6 Thermal Evaluations . . . . . . . . . . . . . . . . 6-7 VII. M an ag ement and C on tro l . . . . . . . . . . . . . . . ' . . . . . 7-1 A. Org ani z ati on . . . . . . . . . . . . . . . . . . . . . . . 7-1 j B. Progran and Cost Control System . . . . . . . . . . . . . 7-6 C. Reports . . . . . . . . . . . . . . . . . . . . . . . . 7-7 D. Progranaatic Authority . . . . . . . . . . . . . . . . . . 7-8 l
Appendix A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 A. Safety Consi deration . . . . . . . . . . . . . . . . . . . . A-1 Tables:
l
- 1. Radiation Exposure i
- 2. Uncontrolled Chemical Reactions
- 3. Industrial Hazards 4 Loss of Services I
J RHO-CD-882 i l
l I. INTRODUCTION )
1 l
. PACKGROUND -
The fuel reprocessing facility at the Western New York Nuclear Service Center near West Valley, New York, began operatica in 1966 under contract to Nuclear Fuel Services, Inc. (NFS). In 1972, NFS shut down the fuel processing f acility for modification and upgrading. During this I period of operation, about 600,000 gallons of high-level radioactive waste were generated as a by-product of the recovery of plutonium and uranium.
Presently, there are stored at the West Valley Plant 560,000 gallons of high-level neutralized waste (530,000 gallons of supernate; 30,000 gallons of sludge), and 12,000 gallons of acid thorium waste. The neutralized waste is stored in a single 750,000-gallon carbon steel tank and the acid waste is contained in a 15,000-gallon stainless steel tank. Each tank has an identical spare into which the liquid waste can be transferred if l
necessary (Figure I-1). 1 In September 1976, NFS announced its intention to withdraw from reprocessing, and modification work was halted. Surveillance of the waste by NFS has continued under the tems of a contract between NFS and New York State Energy Research and Development Authority and the operating license under the Nuclear Regulatory Commission (PRC).
In Novenber 1978, the NRC requested that Rockwell Hanford Operations l (Rockwell) submit a proposal to inspect the waste storage tanks and vaults ;
and to determine their condition. In addition, the high-level waste was to be sampled and analyzed, and the potential for radionuclide transport through the soil surrounding the tanks was to be studied. In answer to this request, Rockwell submitted a two-phase proposal in January 1979.
The first phase of the proposal was to develop a detailed plan. This plan was prepared and issued by an infomal report, RHO-LD-97, entitled
" Project Plan for Inspection and Evaluation of Nuclear Fuel Services High-Level Wasta Storage System," dated August 1979.
The stated objectives of the project were to:
o Determine the condition of the storage tank and vaults, 1-1 1
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BD-1 8D-2 8D-3 80-4 FIGURE I-I IIIGI-LEVEL WASTE STORAGE FACILITIES e
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L RHO-CD-382 o Characterize the high-level radioactive wastes in the tanks, and o Measure the potential for waste transport.through the soils surrounding the tanks.
On November 15, 1979, the Department of Energy (00E) expressed an interest in ass'uming prograis:;atic and financial responsibility for selected tasks since they supported. a DOE. overall plan to remove NFS wastes, inunobilize them, and place the wastes in interim storage pending final d'sposal in a repository.
Tasks deleted from the prior plan and transferred to DOE are$ ~
Task 1 - Subtasks - Sludge Thickness Measurements and Tank Temperature Measurements. The objectives of these '
subtasks are to measure the interface between super-nate and sludge to determine sludge volumes, and l obtain in tank temperature measurements. l Task 2 - Wasta Characterization - The objective of this task is to analyze and characterize the contents of the two active high-level radioactive waste tanks at l'
West Valley.
This document updates RH040-g7 and reflects changes in budget and scope associated with the elimination of the work transferred to 00E.
NEED The EC has expressed the need for additional information concerning the condition of the high-level waste tanks and their contents. The NRC
. wants to assure that continued storage of the waste in the tanks poses no significant risks pending final disposal.
SIM MRY The Nuclear Regulatory Comission has expressed the need for additional infernation :encarning the condition of the hign-level wasta tanks at the Western New (ork State Nuclear Service center near West Valley, New York.
This information is intended to be used in evaluating the safety of con-tinued storage ano in the development of alternatives fer final disposition f the m ;n-level wasta. 1,3
l r a~ , t* p RH0-CD-882 II. OBJECTIVES The Inspection and Evaluation of West Valley High-Level Waste Storage System consists of three technical tasks, and one support task. The objective of each of these are briefly described below:
o Procram Manacement and Suocort - Ensure that the Program is properly managed, scheduled, and budgeted by providing manage-ment and administrative support. In addition, provide safety, and quality assurance support to ensure that the technical objectives are accomplished within safety and quality assurance guidelines.
Establish the statistical reliability of data generated and provide experimental designs to economize the experimental effort ,
needed to obtain the desired information of the technical tasks.
o Tank and Vault Inspection - To inspect the high level wasts tanks and vaults for cracks, leaks, and corrosion. Determine the corrosiveness of the NFS neutralized waste to carbon steel l l and acid waste to stainless steel and to perfom corrosion l studies and testing to confim or add to the present knowledge l of the condition of the waste tanks and potential future corrosion.
o Soil Transoort Studies - Determine the permability of the soil to high-level radioactive liquid wastes and to measure the 1 retention of radionuclides by the soil. Perform radionuclide transport and release modeling to assess hazards associated with waste storage.
o Thermal Evaluation - Obtain thermal data which will allow more accurate and reliable predictions of tank temperatures assoc-iatedwithvariousalternativesformanyingthehigh-level waste and to obtain an estimate of the total heat generation rate of the waste in the tanks, independent of that obtained from radiochemical analysi3 2-1
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p RHO-CD-882 i
The information obtained will be used to evaluate the safety of
! continued in-tank storage and provide a basis and tools for evaluating alternatives for final disposition of the wastes, i
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RHO-CD-882 III. 3 COPE The two carbon steel waste tanks at the West Valley Plant (Tanks 80-1 and 80-2) will be inspected. The need for in situ and laboratory corro-sion tests will be evaluated and performed as necessary to assess present and future integrity of the tanks. Soil transport studies will be con-ducted in the vicinity of the high-level " waste storage tanks to determine the consequences of hypothetical tank leakage. Soil thermal properties and the total heat generation rate of the high-level waste will be, -
measured, a
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. l RH0-CD-882 IV. PROGRAM DESCRIPTION i The project to inspect and evaluate the West Valley (NFS) waste storage system consists of two phases: Phase I - Plan Development and Phase II - Implementation. Phase I consisted of developing a plan for carrying out the work tasks identified for Phase II. This' plan, prepared and issu d by an informal report, RHO-LD-97, entitled " Project Plan for Inspection and Evaluation of Nuclear Fuel Services High-Level Waste Storage System," dated August 1979, is now superseded by this Document RHO-CD-882.
The work required to accomplish Phase II of the program consists of three technical activities and one support activity:
o Program Management and Support o Tank and Vault Inspection o Soil Transport Studies o Thermal Evaluation This section contains the bases, assumption, work breakdown struc-ture, and a narrative description of the activities, l
A. BASES:
The program plan and schedule is _ based on a need to complete essen-tially all work by FY 1982, leaving miminal effort if any for FY 1983.
B. ASSUMPTIONS:
- ~
,. The plan assumes that it is acceptable for Rockwell to perform most nf the specialized technical field work at West Valley with licenced operator support by NFS, and further that no significant delays will result as the present lease at West Valley expires, and a new lease is negotiated and implemented.
C. WORK 3REAKDOWN STRUCTURE:
The work breakdown structure for Inspection and Evaluation of Nuclear f
uel Semices High-level Waste Storage System is cased on the four activi-ttes recuired to accomolish Phase II.
4-1
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RHO-CD-682 WORK BREAKDOWN STRUCTURE INSPECTION AND VALUATION OF NSF HIGH LEVEL WASTE STm AGE SYSTEM 1.0 PROGRAM MANAGEMENT AND SUPp0RT 1.1 Program Office 1.1.1 Planning 1.1.2 Control _. .
1.1.3 Reviews / Approvals - - -
1.1.4 Reporting 1.2 Program Business Management 1.2.1 Cost Control 1.2.2 Report Preparation 1.2.3 Scheduling 1.3 Health, Safety and Environment 1.3.1 Safety Analyses 1.3.2 Procedure Review 1.3.3 Permit / Application and Approval 1.3.4 Radiation Monitoring Support 1.3.5 Environmental Monitoring and Suppcrt 1.4 Quality Assurance 1.4.1 Procurement Support 1.4.2 Design and Fab Suppcet 2.0 TANK AND VAULT INSPECTION 2.1 Photographic Inspection of Tank Interior 2.1.1 Equipment Development 2.1.2 Decontamination and Waste Disposal Plan .
2.1.3 Procedures 2.1.4 Staffing and Training
- 2.1.5 Field Operations 2.2 Photographic and Television Inspection of Vault Annulus and .
Tank Exterior 2.2.1 Ecuioment Development 2.2.2 Decontamination and Waste Disposal Plan 2.2.3 Procedures 2.2.4 Staffing and Training 2.2.5 . leid Operations l
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4-2
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2.3 Wall Thickness Measurement 1 2.3.1 Ecuipment Development 2.3.2 Decontamination and Waste Disposal Plan '
2.3.3 Procedures l 2.3.4 Staffing and Training l 2.3.5 Field Operations '
l 2.4 Interpretation of Vault Structural Inspection Data 2.4.1 Tank and Vault Inspectio,n Statistical Support 2.4.2 Data Evaluations and Reporting 2.5 Corrosion Studies ,
2.5.1 Data Review --
l 2.5.2 Corrosion Studies 2.5.3 Corrosion Studies Statist::al Support 3.0 SOIL TRANSPORT STUDIES 3.1 Soil Sampling and Drilling 3.1.1 Samoling and Analyses Pla. i 3.1.2 Equipment Development '
3.1.3 Procedures 3.1.4 Staffing and Training 3.1.5 Field Operations 3.1.6 Statistical Support 3.1.7 Data Evaluation and Reporting 3.2 Vadose Zone Hydraulic Studies 3.2.1 Equipment Development 3.2.2 Procedures 3.2.3 Staffing and Training 3.2.4 Field Operations )
3.2.5 Statistical Support 1 3.2.6 Data Evaluation and Reporting 3.3 Soil Sorption and Transport Studies 3.3.1 Procedures 3.3.2 Staffing and Training ,
3.3.3 Field Operations l l
3.3.4 Statistical Support 1 l 3.3.5 Data Evaluation and Reporting l 3.4 Modeling of Release Scenarious 3.4.1 Procedures 3.4.2 Statistical Support
( 3.4.3 Data Evaluation and Recorting l
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4-3 1
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RHO-CD-832 4.0 THERMAL EVALUATICN 4.1 Soil Thermal Conductivity Measurement 4.1.1 Equipment Development 4.1.2 Procedure 4.1.3 Staffing and Training 4.1.4 Field Operations 4.1.5 Statistical Support 4.1.6 Data Evaluation and Reporting 4.2 Soil Heat Flux Measurement 4.2.1 Equipment Development 4.2.2 Procedures --
4.2.3 Staffing and Training 4.2.4 Field Operations 4.2.5 Statistical Support 4.2.6 Data Evaluation and Reporting 4.3 Tank Ventilation Heat Loss Measurement 4.3.1 Procedures 4.3.2 Staffing and Training 4.3 3 Field Operations 4.3.4 Statistical Support 4.3.5 Data Evaluation and Reporting 4.4 Downward Heat Flow Calculation
. 4.4.1 Data Review 4.4.2 Heat Flow Calculations 4.4.3 Statistical Support l .
l a-4
RH0-CD-882 D. NARRATIVE:
This section presents a narrative description of the progransnatic objective and scope for each activity, followed by a detailed description of the work to be perfomed at the subactivity level.
INSPECTION AND EVALUATION OF NUCLEAR FUEL SERVICES HIGH-LEVEL WASTE STORAGE SYSTEM.
ACTIVITY - 1.0 - PROGRAM MANAGEMENT AND eiPPORT Obiective: m Ensure that the program is properly managed, scheduled, and budgeted by providing management and administrative support. In addition provide safety, quality assurance, and statistical support to ensure that the technical objectives of the program are accomplished within safety and quality assurance guidelines.
Scooe:
Program Office. Program Management is a level of effort task con-tinuing through completion of the project. The scope includes coordi-nation of the work with the customer and preparation of management reports for communicating the status, progress, and variances of the work accom-plished as compared to the baseline plans contained in the Program Plan.
Full responsibility for management of this project is assigned to Rockwell's Waste Technology Program Office.
Procram Business Manacement. Provide program administrative support
. to the program office by the development of accurate monthly and special cost data and analyses. Prepare program schedules and reports as required.
- . Health. Safety and Environment. Will review procedures for confor-mance to both West- Valley and Rockwell safety standards; perform safety analyses of work to be carried out at West Valley; recommend appropriate safety requirements to be generated in those situations not covered by existing safety regulations; and provide cooiet of procedures for coerations at West Valley for their safety review and approval.
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I RHO-CD-SS2 Quality Assurance. Review procedures for method, technique, calibra-tion requirements, and operator certification.
Work Desc-iotions:
Program Office. The Project Manager will represent Rockwell in all l project matters with the customer. A program plan will be prepared and maintained wr,1ch defines the cojectivesr, technical schedule, financial requirements, and constraints of the overall project and the major tasks.
Work packages and budgets will be prepared and issued _to Rockwell ,
functional organizations and other participants in the project.
The project manager will maintain liaison among West Valley 0peration, New York State Energy Office, and the Nuclear Regulatory Comission.
A management sumary report describing project status, progress, and variances will be issued by the 15th day of each month. This report l consists of a brief narrative on project progress during the reporting l period, identification of problems and actions taken to resolve them, and
.the nature of major work items scheduled for near-term action. In addi-tion, a graphic presentation of budget versus cost, a milestone status display, and an explanation of any variances are included.
Topical reports will be issued to document completion of work.
Technical overview of the work will be assigned to a project engineer who will be responsible for tecnnical direction of the work within the Research and Engineering Function.
program Business Management. Provide program administrative support to the program office by development of monthly and special cost data analyses. Prepare program schedules and reports as required.
Saft:ty. As detailed work procedures are generated they will be reviewed for conformance to existing safety standards at Rockwell and West Valley and safety analysis reports will be written. Appropriate safety and radiation exposure control measures will be recomended for 4-6
RHO-CD-882 those situations not covered by existing safety regulations. After the procedures and safety analysis reports are reviewed and released by Rockwell they will be transmitted to West Valley for review and approval if operations at West Valley are involved.
Quality Assurance. Procedures and related documents will be reviewed for quality requirements. As a minimum the procedures will be reviewed for the following:
- Completeness of task and technique description;
- Calibration and certification requirements;
- Proper acceptance or rejection criteria; and ;
Repeatability f actors or requirements.
ACTIVITY - 2.0 - TANK AND VAULT INSPECTION Objective:
Inspection of the carbon steel tanks, 80-1 and 80-2, and the associ-ated concrete vaults will be carried out using photography, television, and ultrasonic sensors. Due to limited access, only a portion of the tank
~
and vault surf aces can be readily inspected. Documented structural data will be reviewed, and the results of the tank and vault inspection will be evaluated. The tritium content of water vapor in the tank annuli will be monitored as an auxiliary method for detecting tank leaks.
Corrosion studies to determine the corrosiveness of the NFS neutra-lized waste to carbon steel and acid waste to stainless steel will be done to confirm or add to the present knowledge of the condition of the waste tanks. Data characterizing NFS wastes will be obtained from a parallel D'0E program at NFS set forth in RHO-CD-883, entitled, " Nuclear Fuel l Services Waste Characterization and Waste Removal System," Program Plan.
l l Scooe:
Inspection of the carbon steel tanks (801 and 802) and associated concrete vaults (Figure V-1) will be carried out using photography, tele-vision and ultrasonic sensors. Due to limited access, only a portion of l 4-7 l
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STORAGE SUPPORT' COLUMN TANK (TYPICAL OF 6)
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RHO-CD-882 the outer tank surf aces and vault surf aces will be inspected. Documented structural data will be interpreted. Tritiun levels in the tank annuli will be measured as additional means of detecting tank leaks.
Two tasks comprise the work scope for corrosion studies (1) Waste tank fabrication records, heat treatment records, and previous NF5 corrosion testing will be reviewed to help assess present tank integrity and the need for follow-on laboratory and in-tank corrosion testing.
(2) Prestressed corrosion coupons will be inspected after imersion in Tank 8D-2 to measure susceptability to stress corrosion cracking.
Work
Description:
Photoorachic Insoection of the Tank Interiors. Photographic inspec-tion will be accomplished using a Rockwell Hanford Operations (Rockwell) designed photographic system. The system can be tilted so that most of the tank interior, including the tank roof, can be photographed. In-tank photography will be made from the two risers available within the tank which have a diameter greater than 12-inches. Since radiation levels effecting the quality of photography are expected to be significantly above those experienced at Hanford, camera shielding will be required. A -
modification to an existing Rockwell design will be made and a system fabricated for use at West Valley. Photography requires that the air inside the tank and vault be clear. Therefore, the vapor space may hwe to be ex'hausted before photographs can be taken. Costs reflecting the possible need for a ventilation system have not been included, however equipment to perform the ventilation has been developed and used to ,
. exhaust Hanford high-level waste tanks. Preliminary estimates indicate costs for a ventilation system amount to $150,000.
Photograohic and Television Insoection of Vault and Tank Exterior.
Inspection of thi~ exteriors of Tanks 80-1 and 80-2 and the surrounding concrete vaults will be accomolished using a small radiation tolerant television camera and 35m photograonic camera inserted into the annuli between the tanks and the surrcunding vaults. Risers are available for access into each annulus (Figure 17-2). This access limitation will 1-3
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RH0-CD-882 result in about 5-6 percent of the surf ace being available for inspection. Should inspection of more surface area become desirable, additional engineering and equipment will be necessary in order to move away from the access risers by means of a remote controlled carriage. The annular space in 802 will need to be relatively clear of steam for successful imaging, therefore exhausting may be necessary.
Wall Thickness Measurements. Construction records will be studied to determine the expected thickness variations to be encountered in the tank walls. Test coupons with known flaws will be measured in order to determine the limits of sensitivity of the ultrasonic test (UT) system for detecting pitting, scaling, and cracking.
A positioning system (carriage and controls) for the UT detector head will be fabricated, and tested. The positioning system must be capable of entering the annulus access port, and provide position infomation and wall condition data from the top to the bottom of the tank over a path at least 6 feet wide. If required, a rotary wire brush will be incorporated into the UT detector head for removal of any loose surf ace scale. A thermocouple will be incorporated into the UT detector head carriage to provide' temperature data. Testing will be done initially at Hanford.
After testing, the equipment will be sent to West Valley for installation, checkout, and use on Tanks 80-1 and 80-2. '
The required extent of wall thickness and corrosion measurement will be defined as a result of an investigation of the tank's history and the results of photographic and television inspections. The tank's opera-tional history will be investigated, as the area intnediately above any liquid level that was maintained for a period of months is of particular interest.
The photographic and television inspection results will be used to determine potential areas of corrosion or leaks and location of weld seams. The nunter of thickness measurements required and the location of each measurement can then be defined. Wall thickness measurements will be made first on the spare tank, and a duplicate run will chen be made on the active tank.
4-11
L RH0-CD-882 Wall thickness measurements will be compared with construction records on the thickness variation that could be expected in the original construction material. In addition, the results will be compared with the i corrosion predictions based on the laboratory stucies. Finally, the data from the active and inactive tanks will be compared to assist in assessing tank integrity.
Interoretation of Vault Structural Insoection Data. A review will be made of structural and concrete specifications, static and dynamic design loads, thermal loads and thermal cycles, ground water chemistry, con-struction reports, and consultant reports of the vault floating incident.
A failure mode analysis will be prepared. Conclusions from this and prior seismic analysis (l) will be used in conjunction with photographic examination data. The evaluation will be documented in the final report for this task.
An additional potential method for detecting possible tank leaks, is )
monitoring tritium concentrations in the atmosphere of the tank annulus.
Tritium will be monitored by drawing air from the annulus through a column of silica gel. The silica gel will absorb water vapor including tritium water vapor, if present. Periodically a portion of the silica gel will be added to a liquid scintillant and counted in a scintillation counter. An
' increase of the tritium level in the tank annulus would indicate a tank leak. An absence of tritium may not be meaningful since the leak could be too small for detection or tritium may be absent. Equipment for measuring tritium in gaseous streams has been developed at DOE's Idaho Falls site l and is being adapted for use at Hanford.
Corrosion Studies. Waste tank design and fabrication records will be reviewed to identify tank wall areas that would be potential sites for preferential corrosion. Previous corrosion testing that has been con-ducted by NFS will be reviewed. Relevant corrosion literature will be reviewed as an aid in assessing present waste tank condition. The carbon steel Tank 30-2 was stress-relieved following comoletion of fabrication.
A review of the stress relief records is planned to determine adequacy of 4-12 -
1 l
RH0-CD-882 the heat treating procedure. Assuming that the stress relief was complete and the waste tank was not subsequently restressed, the occurrence of stress corrosion cracking (SCC) would not be expected. However, movement of the tank after it was stress relieved may have restressed portions of it.
Three forms of corrosion attack have been of concern in carbon steel waste storage tanks containing alkaline nitrate wastes located both at Hanford and Savannah River Plant (SRP). These are general corrosion, pitting, and stress corrosion cracking (SCC).
Observed general corrosion has been slight in laboratory and in-tank corrosion testing at Hanford anc SRP. Pitting attack has been observed in laboratory tests and on coupons exposed to the vapor phase in some single shell tanks at Hanford. In all cases, the attack was slight. SRP, pitting caused failure of cooling coils in some tanks after sluicing.
Negligible pitting or general corrosion has been observed on welded coupons presently being exposed to the contents of Tank 8D-2 at NFS.
Apparent stress corrosion cracking has been observed in several of the f ailed storage tanks at SRP. This type of failure has been postulated as the mode of failure for failed single-shell tanks at Hanford but has not been visually verified.
Nitrate induced stress crossion cracking, as a potential node of failure of storage tanks containing alkaline nitrate waste solution, remains a concern. Personnel at Savannah River Laboratory (SRL) have conducted stress corrosion cracking tests which have led to the adoption of waste composition limits for OH , NO3 and NO2 within whien
, stress corrosion cracking is not expected.
Even though the 80-2 waste tank was stress relieved following construction, subsequent settling and movement of the primary tank may have reintroduced tensile stresses of sufficient magnitude to promote stress corrosion cracking if the waste composition lies in the undesirable range. Since full analysis of the NFS waste solution will not be known until late FY 1981 evaluation of the stress corrosion cracking propensity from the waste ccmoosition will be delayed.
4-13
F RHO-CD-882 In-tank exposure of a set of precracked stressed carbon steel speci-mens is planned. To measure the susceptability of stressed carbon steel to nitrate induced stress corrosion cracking, modified wedge open loaded (WOL) specimens that contain a fatigue crack will be used. The machined specimens contain a bolt that when tightened puts the . crack tip under tensile stress. Corrosion testing plans will be prepared, however it is anticipated that specimens will be inrnersed in the tank solution, sus-pended from stainless steel wires, and a set will be retrieved aeriodically to measure any crack growth. It is planned that duplicate specimens will be retrieved at regular intervals of increasing exposure. The exposure periods can be changed or the tests terminated at any time depending on the test results. With this type of specimen, the stress at the crack tip decreases with crack length. Therefore, the threshold stress intensity, K SCC (the minimum stress intensity necessary to cause stress corrosion cracking), is the K value found when the crack ceases to grow. The ini-tial value of K is calculated by relating the load provided by the bolt to the crack opening and length. Final reporting of corrosion test results will be three months after test completion. While the report has been scheduled for the end of FY 1983, later reporting may be desirable if extended testing appears warranted. !
The data orived from the above procedure will be of value in l providing a measure of the severity of stress corrosion cracking that can occur if residual stresses are present in the tank wall. Futhermore, this type of testing will remove uncertainties arising from waste solution )
analytical results.
Specimens will be exposed to the NFS alkaline waste solution.
Duplicate samples will be retrieved on a schedule previously described.
The specimens will be decontaminated and transported to the appropriate l laboratory where they will be pulled apart, the crack surf ace examined and crack length measured. ,
l l
4-la
ACTIVITY 3.0 - SOIL TRANSPORT STUDIES Objective:
The objective of the soil transport studies activity is to determine the cermeability of the soil to the high-level radioactive liquid waste and to measure the retention of radionuclides by the soil. Vadose zone 1 hydraulic properties will be measured, and the effect of high-level waste on flow in the vadose zone will be determined. Sorption distribution coefficients for the important radionuclides will be measured as a function of macrocomponent concentration and soil type. Generalized and specified release scenarios will be modeled using measured hydraulic and sorption input parameters.
Scoce Soil Samoling and Drillino. Access tubes for in situ vadose zone hydraulic measurements will be installed. Two wells for obtaining vadose zone soil samles for the laboratory sorption-transport studies and a single well to obtain soil samples of the uppermost ground water aquifer will be drilled, assuming the aquifer exists at a depth relevant to transport studies.
1 Vadose Zone Hydraulic Studies. Vadose zone hydraulic properties
~
determine the effect of high-level waste on flow in the unsaturated soil I zone. I l
Soil Sorption and Transoort Studies. Soil sorption distribution I coefficients (k d) for vadose zone and aquifer soil types will be
~
measured and K d values using either actual or simulated suocrnatant "
.- waste solutions will be verified.
Transoort Modeling of Release Scenarios. Transport models will be used to assess the impact of various release scenarios. Hydraulic and sorption parameter valves measured in the above studies will be used as the input data. Reference release scenarios will be used to set up and calibrate the transport models; and specified release scenarios chosen by agreement with the Nuclear Regulatory Comission (NRC) will be modeled to assess their imt,act on the environment.
4-15 ,
l
4 RHO-CD-882 Work Descriotion Soil Samolino and Drilline. Seven shallow access tubes will be installed in a circular pattern at each of three sites near the tanks for the vadose zone hydraulic studies. Four of the access tubes at each site will be used to monitor water potential as a function of time. Three of the access tubes will be used to monitor moisture content at each site as a function of time. The three sites will be outside of, but adjacent to, the tank f arm fence in an area where the surf ace sediments are represen-tative of tills underlying the waste tanks.
Two wells will be drilled, cased, and grouted to obtain soil samples from the vadose zone for the sorption-transport studies. The vadose zone will be sampled every five feet and at any change in lithology from the soil surf ace to the top of the uppermost aquifer. A single well will be drilled, cased, and grouted to obtain samples of the uppermost aquifer.
The acuffer vill be sampled every five feet. The two vadose zone wells will be drilled. One well will be located as close to the tanks as possible without weakening the tank's foundation. The aquifer sampling well will be located approximately half way between the tank f arm and the nearest surf ace water. Both wells will be grouted and capped to assure that surface water will not be allowed to percolate down or along the side of these wells.
- Vadose Zone Hydraulic Studies. Vadose zone hydraulic properties will be determined at each of the three sites. A barrier will be erected at each site and ponded water will be added. Wetting frontal movement, soil water potential, and water content will be measured as functions of time, The data will be analyzed to estimate the reference vadose zone hydraulic parameters. Following the water test the same type of tests will be made ,
i in the same three wells using simulated waste solutions to determine the 1
effect of the tank wastes on wetting frontal movement, soil water l cotential, and water content as a function of time. The data will be
! analyzed 'to estimate the waste vadose zone hydraulic parameters.
I l
a-15 1
RH0-CD-882 During warm weather each of the three sites will be ponded with water until the wetting front arrives at a selected depth. The site will then be covered with plastic to restrict evaporation and the water potential and water content will be monitored periodically as a function of depth and time. Readings will be taken daily for the first ten days and weekly for six months. Initial estimates of unsaturated hydraulic parameters will be made from unsaturated flow equations. Final estimates of unsaturated flow parameters will be refined from a computer back-fitting routine. Parameters will be used in numerical models with selected boundary conditions to predict regional movement. Estimates will be made of the effect of high-level waste transport properties on unsaturated flow in the system.
Soil Sorption and Transoort Studies. Mechanical analysis of well samples will be used to delineate soil sediment types. Samples of each sediment type will be composited. K d values will be determined as a function of macrocomponent concentrations (Na+, K+, Ca2+, Mg2+ ,
NO2 .
~
NO 3, and HC0 ), Statistical methods will be used to develop predic-tive equations to relate measgred Kd values to equilibrium macroton con-centrations. Transport parameters which control the equilibrium concen-tration of macrocomponents in solution as a function of distance and time following a postulated leak will be determined. Predicted Kd values will be verified using either actual filtered supernatant or simulated supernatant depending upon availability.
Sedimentation procedures will be used to delineate the soil into sediment types. Quartered well sangles will be composited to fonn sediment type samples. Kd values will be measured using batch techniques for strontium-90, cesium-137, technetium-99, neptunium-237, thorium, plutonium and americium as a function of equilibrium macro-component composition for each type. Equations which relate Kd values to the equilibrian solution concentratiuon of macroions will be developed. Soil parameters which control the equilibrium solution concentration of macroions as a function of distance and time from a leak occurrence will be measured using standard soil methcds. These include 4-17 l
h RH0-CD-882 l
ion exchange parameters for Na+, K+, Ca2+ , Mg2 +, cation-exchange capacity and extractable macroion concentrations. Predicted Kd values will be verified using soil column methods and simulated supernatant liquid. Sorption of the critical radionuclide(s) based on source terms obtained from 00E waste characterization studies from the potential dose-to-man stand point will be verified.
Transoort Modelino of Release Scenarios. General! zed and NRC speci-fied release scenarios will be modeled using hydraulic and sorption parameters described in the two previous subactivity as model inputs. The generalized release scenarios will be used to scale the tank, sediment, soil water, and groundwater geometries and calibrate this system. A set l of specified release scenarios will be suggested to the NRC. The NRC can )
pick any or all of the suggested release scenarios and other scenarios that are required to meet their needs. !
Suggested scenarios may include a worst case, a most likely case, and I l
a small leak case. The worst case could be the sudden failure of the tank l and vault resulting in waste under pressure of its hydraulic head being in !
direct contact with the surrounding sediments. After an engineering analysis of the tank-vault system is completed a "best engineering guess" of the most probable leak case could be suggested as a second al ternative. Small leak scenarios could be further suggested cases. A series of scenarios of varying constant leak rates over a period of time could thus be suggested. l The models will be used to calculate the release rates to the biosphere, and dose to man.
ACTIVITY 4.0 - THERMAL EVALUATION Objective: .
The objectives of this activity are to obtain thermal data which will I allow more accurate and reliable predictions of tank temperatures associ-ated with various alternatives for managing the high-level waste and to obtsin an estimate of the total heat generation rate of the waste in the tanks, independent of that obtained from radiochemical analysis, a-18
1 RHO-CD-682 Scoce:
This task will consist of field and laboratory measurements of the thermal properties of the soil surrounding and covering the high-level waste tanks, field measurements of heat flux in the soil covering the tank, and measurement of heat removed by tank ventilation. The measure-ments will continue over a period of one year to determine seasonal vari ations. The measurements will include both the neutralized and acid waste tanks. Predictive temoerature calculations will be made as requested by the NRC.
Work Descriotion:
In order to assess the effects of various possible high-level waste operations, such as liquid removal or in situ solidification, it is nec-essary to predict the resulting temperatures in the tanks and surrounding concrete vaults. Accurate temperature predictions depend upon accurate determination of soil thermal properties and waste heat generation rates.
Soil Thermal Conductivity Measurement. The thermal conductivity of the soil is strongly affected by moisture content and degree of congac-tion. For that reason, in situ conductivity measurements will be made without altering the soil moisture content and bulk density.
In situ measurement of soil thermal conductivity can be done in three l ways: (1) by measuring the temperature rise of an electrically heated sphere buried in the soil; (2) by measuring the temperature rise of a l horizontal heated pipe buried in the soil; or (3) by measuring the rate of temperature rise of a vertical heated pipe or " thermal needle."
The vertical heated pipe or thennal needle was selected because results, accurate to within 5 percent, can be obtained economically and quickly without disturbing the soil. This method has been widely used to measure soil conductivities prior to designing underground power cable systems, and also has been used in the laboratory to measure the thermal l
conductivities of various solids. The method is particularly well suited to particulate materials. .
I 4-19 l 1
l 1
l 1
r .
RH0-CD-882 PROGRAM AND COST CONTROL Program control, direction and liaison are accomplished through weekly briefing reports, monthly progress reports, and program team meetings.
Technical direction of work being perfomed at the West Valley Plant will be under the direction of the project manager and supervised by the project engineer or his delegate. The NFS P1 ant Manager has overall responsibility for all operations at the West Valley Site and conformance with existing license requirement.
Budgetary control for the program is predicated on the work package system. The work package describes work from the work breakdown structure and establishes both milestones for accomplishing the work and a target funding level for functional organization performing work. The functional organizations affected evaluate the described work and prepare functional planning documents which establish the resources required to accomplish the work within the prescribed limits. After approval of the work pack-ages by the program director and the functional directors, they are entered into an automated data processing system that produces periodic budget reports.
Charges to the program for work performed are authorized by intarnal work orders. Costs incurred are accumulated against work packages and periodically reported to allow a comparison of actual project costs against budgeted costs.
Labor charges against work packages are authorized by internal work orders and are recorded by use of tha time distribution report (TDR).
Purchase orders for material or services reference the authorizing work
. order and the number of the benefiting work package and are reported accordingly, but only when paid or accrued. The lag in reporting costs is
. compensated for by requesting estimates from major subcontractors prior to the end of the month so that these costs can be accrued.
Monthly cumulative budget / cost reports are prepared for the project and are used to measure progress as depicted by planned versus actual resources expended.
7-5
RH0-CD-882 REPORTS l
Weekly reports to the program director are prepared by the project I manager, utilizing inputs from the program team menbers. The most signi-ficant items in this report are incorporated into a report by the program director to the Rockwell general manager.
Each month, an Executive Control Meeting (ECM) is held by the general manager to review the status of all programs and projects. The attendees include all program and functional directors. During the meeting, a sum-mary of the project status, including milestone accomplishment, problems, proposed solutions, and financial status is presented.
A management sumary report is issued to NRC by the 15th day of each month. Thic report consists of a brief narrative on project progress dur-ing the reporting period, identification of problems and actions taken to resolve them, and the nature of work items scheduled for near-term action.
In addition, a graphic presentation of budget versus cost, a milestone status display, and an explanation of any variances are included.
A program plan will be maintained and updated at least annually or at the request of the NRC. The plan will include a description of the equip-ment to be used, its specific application to the West Valley tanks, the ,
estimated cost and schedule for completing the. work, and the specific informantion to be obtained. The plan will. describe the rationable whereby the various techniques for obtaining the infomation were selected, considering the cost effectiveness of the technique.
A program overview report, which sumarizes the current project plan and the status of Dhase II work, will be issued annually. The purpose of the overview report is to infom other government agencies and interested .
pa, ties on the .ork being ,e,fomee at west ,alle, uneer this ,,an.
I 4
77
RHO-CD-882 PROGRAMATIC AUTHORITY Program authority is vested solely in the program director, with responsibility for management of the program delegated to the project man-ager. All customer contacts concerning the project are made by the prograr director or project manager, or with their concurrence. No data or reports generated as a direct result of project work or relating to the project in any way are to be disseminated to the customer, the public, or the scientific community without the explicit approval of the program dir-ector and PRC. Reports generated by functional organizations for internal Rockwell distribution will be approved by the project manager prior to distribution. Reports and data prepared by onsite/offsite contractors or consultants must be approved by the program office prior to publication or distribution.
e 7-8
RHO-CD-882 APPENDIX A SAFETY CONSIDERATIONS Operations required to perform the three technical tasks, proposed for evaluations of the Nuclear Fuel Services High-Level Waste Storage Tanks, have been reviewed to identify potential hazards which could result in abnormal radiation exposure and/or radioactive contamination of personnel performing the tasks, release of radioactivily to the environs,'
physical injury, and equipment or f acility damage.
TASK DESCRIPTIONS o Tank and Vault Inspection. - This task will remove access port riser plugs to allow insertion of inspection equipment into a tank annulus, a tank vapor space, the t- waste contents, and into the vault area. A still and/or te.. vision canera will be used to provide photographic inspection of the vaults and of tank wall and roof sections. Ultrasonic sensors will be used to measure tank wall thickness.
Renoval and replacement of an access port plug from tanks 80-2 I
and 80-4 will be required for inspection of several sets of corrosion test coupons, surpanded from stainless steel wires, into the liquid waste solution. Duplicate sets of test coupons will be retrieved for laboratory examination and testing at specified periods.
o Soil Transport Studies. - Consercial well drilling equipment will be used for drilling wells for soil-sampling of the vadose zone and of the uppermost groundwater aquifer. , Access tubes for in situ vadose zone hydraulic measurements will also be installed at three sites.
A-1
. . l l \
l l
RHO-CD-882 !
I l
o Thermal Evaluation - Shallow holes ( 8' deep) will be drilled over and near the tank vaults for e@lacement of one or more themal needles and a network of therinocouples. Manual drilling, using the extension handled post hole auger is being considered for drilling the emplacement holes.
EQUIPMENT DESIGN AND TESTING Inspection and sampling equipment, test corrosion coupon installation and retrieval equipment, and their auxilaries will be designed for opera-tion in high-leved radiation fields and/or for remote operation as neces-sary. Such equipment will also be designed to meet or exceed applicable industrial standards for operational safety. Radiation shielding will be incorpo ated to reduce radiation exposure of operating personnel to pre-detemined allowable limits.
Retrieval and/or disposal of this equipment must also be possible without undue risk of abnormal radiation exposure or spread of radioactive contamination of the environs.
Prior to use equipment will be tested to assure that it can be oper-ated without undue risk cf abnormal radiation exposure to operating person-nel, damage or disruption of existing waste storage tank systems, or conta-mination of the environs, j
OPERATIONS All activities' associated with these tasks will be performed in accor-ance with approved operating procedures. In-addition to operating instruc-tions, the procedures will contain pertinent safety requirements such as:
l 1
- a. Equipment' capabilities and requirements for removal of access )
port plugs. Safety requirements to minimize risk of dropping .
l the plug, and for protection of personnel from physical injury l and from abnormal radiation exposure and/or radioactive contamination. l l
A-2 4
_ _ . . _ , , , , , , -m- - - --- x - r
RHO-CD-882
- b. Weight restrictions for equipment placed on vault top areas.
- c. Protective covering of the area surrocnding the access port to N event surf ace and/or at:nospheric contamination (e.g., plastic !
sheeting, greenhouse).
- d. Regulation of the ventilation exhaust system and/or bleed-in air such that tank vacuum is maintained sufficient to prevent vapor exhaust from an open tank access port,
- e. Protective clothing, respiratory protection,-and other..personne4 safety devices 'a be used.
- f. Administrative controls and/or shielding requirements for_ work in the vicinity of the oper. access port to minimize personnel radiation exposure,
- g. Expected personnel response to emergency situations.
Procedures for each of the operations must not only cover the spect-fics of equipment insertion and operation, but must also cove its removal and the requirements for handling and disposal of potentially high-level radioactively contaminated equipment. -
ACCIDENT ANALYSIS Hazards identified for the operations to be conducted are radiation exposure, uncontrolled chemical reactions, incustrial, and loss of utili-ties and ' services. Tables 1-4 list the hazard, event sequences, consequ-ences, and preventative / ameliorative measures.
The maximum credible accident resulting from these operations is postulated to be the inadvertent transfer and spill of up to one litar of waste tank supernatant during retrieval of equipment from the 80-2 Tank access port.
o Accident Scenario During photography in the 80-2 tank vapor space, the camera and its protective cover are innersed in the waste tank supernatant The protective cover is damaged, allowing the cover and/or the
. A-3
RHO-CD-882 camera to fill with , liquid waste. Up to a liter of waste supernatant (approximately 7 C1/ liter 137 C s) is spilled outside the access port
~
during retrieval operations.
o Consecuences A spill of liquid waste containing 7 Ci of 137Cs would subject personnel to a gama dose rate of approximately 2 R/ hour at 3 feet, and if uncontained by protective covering around the I access port, could require a significant decontamination effort. Based on methods used to estimate releases from spills at Hanford, it is assumed that 10~4 fraction of the cesium (700 C1) would be released to the atmosphere.* This release is equivalent to that released from loss of 80-2 tank ventilation for about 4 minutes, as shown in the NFS Safety Analysis Report (60 ml/second vapor release 9 approximately .05 C1/ milliliter)*
Atmosphere concentration of 137Cs resulting from this accident should not exceed 10 CFR 20 Appendix B, Table II Guides, at the site boundary.
o Detee' tion Such a spill would be detected by Radiation Monitoring personnel providing surveillance of the Task I activities.
o Corrective Action Initially, efforts would be directed to reduce the radiation dose rate and to contain the spill. The access port would also be closed. Recovery would involve transfer of the contaminated eqt,1pment, contaminated protective cover materials and/or soil to a solid waste burial container.
- RHO-C-4, "Probalilistic Risk Analysis of the Operation of the Purex Plant", J. Allgeier, et al., Science Applications, Inc., October 1977.
A-4 w
e -
RHO-CD-882 o Effects on Other Systems Tank and Vault Inspection efforts would be suspended until clean-up activities were completed. Personnel radiation exposures may require additional manpower; however, other NFS activities should not be affected.
~
- 0ccket Number 50-201 " Safety Analysis Report NFS' Reprocessing Plant West Valley, New York", Volume II, 1973.
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ll tess of Electrical Feuer 1) Electrical peuer to the esaste la) Waste las eestilaties is Best. I Close means part if spee. At storage led area is lost. Iast (1-3) u tleltles batted. duun all fa 4 u tisilles, ht dame att sistelators and other sle-Possible escape of espers at telaters and other sewses of air s appreslaately 5 a le Z e48/mi to envirees. to tant. Ier Feevide aperellen of emesseur rw=er Ihe eentilasles system. y
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- rn 25 tons of 8 task Air 2) Electrical er compresser 2) Potential for redlemtive 2) utllise' sten.any sospeesser, ettlise N f allwe. malertal depeeltles thre@ self-contaleed he aething alt systee Inhalatlen. Iem uste pesseeeel.
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% N RH0-co-882 Ei.ECTRICAL CONNECTIONS e/soos , omson .
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=: HEATER &,THERMOCOUPLES gir 3:;.
V DRIVE POINT. FIGURE IV-3 THERftAL CCt!CUCTIVITY PROBE l 4-20 l
- h RHO-CD-882 The thermal needle or probe is a pipe with a length at least 50 times granter than its diameter. The pipe contains an electric heater which occupies the entire length of the pipe. A temperature measuring device, such as a themocouple or thermistor, is located inside the pipe at the i
mi d-poi nt. Figure IV-3 shows one design of a thennal conductivity probe. Af ter drilling 'a pilot hole the needle is pressed into the ground and electric power to the needle heater is turned on and kept at a constant, i measured level. The temperature of the needle is recorded as a function of time and the thermal conductivity of the surrounding soil is calculated from the temperature-time record using established mathematical relations.(2) Bulk soil density and heat capacity will be measured in l the laboratory using standard gravimetric and calorimetric methods. Soil Heat Flux Measurement. Once the soil thermal conductivity is i known, the rate of heat flow from the tanks to the surf ace may be determined by measuring the tencerature gradient in the soil covering the tanks. The temperature gradient will be measured by placing thermocouples at known depths at various lccations over and near the tank vault. Tank Ventilation Heat loss Measurement. In order to determine the total heat generation rate, it is also necessary to determine the heat removed by tank ventilation and by conduction downward through the bottom of the tank and vaults. The heat removed by tank ventilation will first be estimated from the amount of water condensed from the exhaust air by j the offgas condensers. If more accuracy is desired, tt ? heat removed by l tank ventilation will be determined by measuring the flow rate, tempera-ture, and humidity of the air exhausted from the tanks. Measurements will be taken close to the tanks to minimize error due to heat loss from the duct; however, new penetrations into the exhaust duct would be reouired. Downward Heat Flow Calculation. The rate of heat conduction downward through the tank bottom cannot be measured directly, but will be estimated from temperature profiles calculated from the HEATING 5(3) conduction code using measured tank temperatures and soil orocerties as input data. s i A-21 l
t b . RHO-CD-882 The amount of heat conduction downward should be relatively small so that uncertainty in its value should not introduce serious error in the deter-mination of the total waste heat generation rate. At the request of the NPC, temperature calculations may be carried out to assess the themal consequences of postulated waste management operations. O e e dW. l 4-22
- 1 I
1
o n . RHO-CD-882 REFERENCES
- 1. UCRL-52485, May 1978, Davito A. M. and Coworkers, " Seismic Analysis of High-Level Neutralized Liquid Waste Tanks at the Western New York State Nuclear Service Center, West Valley, New York."
- 2. H. S. Carslaw and J. C. Jaeger, " Conduction of Heat in Solids," Second Edition, Oxford Press (1959), p. 261.
- 3. W. D. Turner, D. C Elrod, and I. I. Simon-Tov, " HEATING 5 - An IBM 360 Heat Conduction Program," ORNL/CSD/TM-15, March 1977.
e 9
- 4-23
RHO-CD-882 V. PROGRAM SCHECULE Table V-1 provides a listing of monthly milestones, against which Rockwell will report status in the monthly report. Figure VI-1 displays i the Master Program Schedule. This schedule reflects the long-term plan for accomplishment of the milestones established for the Program. et i
)
l l O O h 5-1 I i
i RHO-CD-882 TABLE V-1. Monthly Milestone Schedule Scheduled i 1.0 Program Management and Support 1.1 Final Program Plan Issued 3-25-80 1.1 Program Plan Revision Issued 12-80
! 1.1 Program Plan Revision Issued 12-81 1.1 Program Plan Revision Issued 12-82 2.0 Tank and Vault Inspection 2.1 Procedures for Photographic-In-Tank Inspection Issued 5-15-80 2.2 Procedures for Inspection of Vault Annulus and Tank Exterior Issued 6-15-80 2.1 Photographic-In-Tank and Annulus Inspection Completed 9-26-80 2.2 Tank Inspection Completed 9-26-80 l 2.5 Data Reviews Completed 3-81 '
2.3 Procedure for Wall Thickness Measurement Issued 7-81 2.5 Initiate Corrosion Testing 8-81 2.5 Corrosion Testing Completed 6-83* 2.3 Wall Thickness Measurement Completed 7-82 2.4 Tank and Vault Inspection Report Issued 12-82 2.5 Topical Report on Corrosion Testing Issued 9-83* 3.0 Soil Transport Studies 3.1 Procedure for Soil Sampling and Drilling Issued 1-82 3.1 Soil Sampling and Drilling Completed 4-82 3.1 Soil Sampling Interim Report Issued 8-82 3.2 Vadose Zone Hydraulic Measurements Completed 9-82 3.3 Kd Valves by Mechanical Analysis Completed 9-82 3.2 Hydraulic Measurement Interim Repcrt . Issued 11-82 3.3 Verification Tests Completed 4-83 3.4 Modeling Completed 7-83 3.3 Topical Report or Soil Sorption and Transport Measurements Issued 9-83 4.0 Thermal Evaluation 4.3 Procedure for Tank Ventilation Heat Loss Measurement Issued 3-81 4.2 Procedure for Soil Heat Flux Measurement Issued 4-81
- Preliminary schedule. Test results may recuire rescheduling 5-2
? -
. . e RHO-CD-882 4.0 Thermal Evaluation (continued) 4.1 Procedure for Soil Thermal Conductivity Measurement Issued 5-81 4.3 Heat Loss Testing at Hanford Comoleted 6-81 4.2 Installation of Thermoccuoles Comoleted 6-81 4.1 Fabrication of the Thermal Probe Completed 7-31 4.1 Soil Thermal Conductivity Measurements Complete 4/82 4.2 Soil Heat Flux Measurements Comoleted 4/82 4.1 Soil Thermal Conductivity' Interim Report Issued 7/92 4.2 Soil Heat Flux Measurement Interim Report Issued - - 7/82 '~
e 4.4 Downward Heat Flow Calculated 7/82 4.3 Tank Ventilation Heat Loss Measurements Completed and Topical Report Issued 12/82 I e e o e 5-3 e
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RH0-CD-882 VI. RESOURCE REQUIREMENTS Cost Plans have been prepared for Fiscal Years 1980 through 1983. . Budget guidance furnished by the NRC set operating cost limits for FY 1980 and FY 1981 of $625,000 and $1,000,000 respectively.. Work during FY 1982 was scheduled to essentially complete all remaining work using FY 1983 for a windup of remaining items, primarily reporting. Cost data for Fiscal Year 1981 and beyond should be considered preliminary and subject to review and possible change during subsequent program plan up dates later in 1980. Information is presented by both Activity and Cost Element for each l Fiscal Year. l l 9 l b9 m 1 . . 6-1 l 1
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RHO-CD-882 TABLE VI-1 SUDGET SUf9%RY BE ACTIVITIES (Dollars in Thousands) ACTIVITY FY 1980 FY 1981 FY 1982 FY 1983 1.0 Program Management and Support $ 95 $ 105 $ 145 $ 22 2.0 Tank and Vault Inspection 5 30 7 64 120 67 3.0 Soil Transport Studies 745 192 4.0 Thermal Evaluation 131 95 46 TOTAL $ 625 $1,000 $1,105 $ 327 [' s_ e 4* m
. 5-2
RH0-CD-882 TABLE VI-2 RESOURCE REQUIREMENTS SY COST ELEMENT (Dollars in Thousands) OPERATING EXPENSE FY 1980 FY 1981 FY 1982 FY 1983 Direct Labor Cost (Rockwell) $ 231 $ 214 $ 351 3 58 Materials and Supplies 35 10 25 Equipment 28 196 81 - Travel and Living 14 17 26 Contracts:
- a. Nuclear Fuel Services 35 50 76
- b. J. A. Jones Construction 15
- c. Vault Failure Mode Analysis 65 ;
- d. Corrosion Studies 30 20 28 '
- e. Drilling 20 ,
- f. Consultants 21 l
- g. Boeing Computer Services l Richland 20 98 Material Procurement 10 28 21 10 Subtotal Direct Costs 3 368 $ 610 $ 661 $ 194 Functional Overheads ~ 21 170 203 62 G&A/ Common Support t36 220 241 71 TOTAL COSTS $ 625 $1,000 $1,105 $ 327 l
t e i w 6-3 1
-- m RHO-CD-882 IABLE VI-3 )
RESOURCE REQUIREMENTS ACTIVITY 1.0 PfiOGRAM MANAGEMENT AND SUPPORT FY 1980 FY 1981 FY 1982 FY 1983 MANPOWER (1) Rockwell Hanford Operations 15 16 21 4 OPERATING EXPENSES Direct Labor Cost (Rockwell) $ 45 $ 51 3 68 $ 13 Materials and Supplies Equipment Travel and Living 3 3 7 Contracts: Material Procurement Subtotal Direct Costs 48 54 75 13 Functional Overheads 26 29 38 4 G&A/ Common Support 21 22 32 5 TOTAL COSTS (Dollars in $300) $ 95 $ 105 $ 145 $ 22 (1) Average Equivalen't Mannonths amou n a g me M m-6-4
RHO-CD-882 TABLE VI-4 RESOURCE REQUIREMENTS ACTIVITY 2.0 TANK AND VAULT INSPECTION FY 1980 FY 1981 FY 1982 FY 1983 MANP06FT.(1) Rockwell Hanford Operations 64 40 10 3 OPERATING EXPENSES Direct Labor Cost (Rockwell) $ 186 $ 23 $ 36 $ 9 Materials and Supplies 35 5 Equipment 28 176 6 Travel and Living 11 11 3 Contracts:
- a. Nuclear Fuel Services 35 40 6
- b. J. A. Jones Construction 15
- c. Vault Failure Mode Analysis 65
- e. Corrosion Studies 30 20 28 Material Procurement 10 24 3 4 Subtotal Direct Costs $ 320 $ 474 $ 74 $ 41 Functional Overheads 94 122 21 12 G&A/ Common Support 116 168 25 14 TOTAL COSTS (Dollars in $000) $ 530 $ 764 $ 120 $ 67 (1) Average Equivalent Mansonths 4
T e 4 6-5 l l
RHO-CD-882 TABLE VI-5 RESOURCE REQUIREMENTS ACTIVITY 3.0 SOIL AND TRANSPORT STUDIES FY 1980 FY 1981 FY 1982 FY 1983 MANPOER (1) Rockwell Hanford Operations 64 7 OPERATING EXPENSES Direct Labor Cost (Rockwell) $ 212 $ 24 Materials and Supplies 25 Equipment 75 Travel and Living 14 Contracts: I
- a. Nuclear Fuel Services 50
- g. Drilling (2) 20
- h. Consultants 21
- 1. Boeing Computer Services Richland 20 83 ,
Material Procurement 17 5 l Subtotal Direct Costs $ 454 $ 112 Functional Overheads 127 38 GIA/Consnon Support _ 16 4 42 TOTAL COSTS (Dollars in $000) $ 745 $ 192 l l 1 (1) Average Equivalent Ma.nonths l (2) Evaluation of Hydrological Test Data
- 2. ;
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- 1 i
6-6.
o . RHO-CD-882 TABLE VI-6 RESOURCE REQUIREMENTS ACTIVITY 4.0 THERMAL EVALUATION FY 1980 FY 1981 FY 1982 FY 1983 MANPJWER (1) Rockwell Hanford Operations 12 4 3 OPERATING EXPENSES Direct Labor Cost (Rockwell) $ 40 $ 35 $ 12 Materials and Supplies 5 Equipment 20 Travel and Living 3 2 Contracts:
- a. Nuclear Fuel Ser~ ices 10 20 1 Boeing Computer fiervices 15 Material Procurement 4 1 1 Subtotal Direct Costs $ 82 3 58 $ 28 Functional Overheads 20 16 8 G&A/Comon Support 29 21 10 TOTAL COSTS (Dollars in $000) $ 131 $ 95 $ 46 (1) Average Equivalent Manmenths O 9e 1
l 1 i 1 e 6-7
I 1 1 1 RH0-CD-882 l l VII. MANAGEMENT AND CONTROL ORGANIZATION The program will be managed using a matrix management organization ; consisting of a program team. The program team is headed by a project manager. The team consists of a project manager, project engineer, activity leaders, and program representatives. The project manager is accountable to the Program Director, Waste Technology, for the successful accomplishment of the project. Tne project engineer is responsible for ! accomplishing major technical objectives of the project. Activity leaders are responsible for planning and directing the work in their assigned tasks. Program representatives represent their respective functional organizations in identifying and acquiring the services needed to support the program. Team menbers are selected by the functional departments and program office. The Nuclear Regulatory Commission (NRC) and Department of Energy, Richland Operations Office (00E-RL) have concurred on the scope of work and assignment of work to Rockwell during the implementation phase. A critical concern on the part of DOE-RL was whether this work would have undesirable impacts on current DOE-RL programs at Hanford, despite the f act that the technical requirements are essentially the same as current Rockwell programs relating the storage of high-level wastes in tank at Hanford. . Both the NRC and Rockwell maintain liason with the DOE-RL during the course of the program ~. Liason is also maintained between Rockwell and Nuclear Fuel Services, Inc. (MFS) and the New York Energy Research and - Development Authority (NYSERDA) who are co-licensees of the Western New York Nuclear Services Center. - Figures VII-1 through VII-4 illustrate. o Rockwell Organization o Waste Technology Program Office o Management Organization o Interfaces 7-1
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