ML20206M610
| ML20206M610 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1986 |
| From: | Clark A NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-32 NUDOCS 8608210273 | |
| Download: ML20206M610 (6) | |
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JUL 17 m Project No. M-32 MEMORANDUM FOR: Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch FROM:
A. Thomas Clark, Jr.
Advanced Fuel and Spent Fuel Licensing Branch
SUBJECT:
REPORT ON V' SIT TO WEST VALLEY--JULY 8, 1986 THROUGH JULY 11, 1986 The agenda for the subject meeting is shown in Attachment 1.
A list of meeting attendees is shown in Attachment 2.
Size Reduction in Fuel Receipt and Storage Area All spent fuel, except Nuclear Fuel Services, Inc., fuel, has been removed from the Fuel Receipt and Storage water-filled pool. Because of uncertainties associated with removal of the remaining fuel, the prime contractor, West Valley Nuclear Services, Inc., has been requested to study a safe method whereby the old, contaminated equipment, being removed from the former reprocessing cells, can De. cut into smaller sizes for more efficient and economical disposal, using the underwater area. Some trial cutting has already taken place to demonstrate the feasibility of the process. The general plan being considered is to move all of the remaining spent fuel into four rows of racks along the west wall nearest the old entry into the Process Mechanical Cell. A shield of six additional racks would remain as a " buffer zone".between the fuel and the cutting operations. All other racks would be removed. ~The Department of Energy indicated a willingness to provide information related to the Commission's conclusions in NUREG/CR-2236, " Seismic Resistance Capacity Evaluation of Spent Fuel Storage Rocks and Fuel at West Valley, New York." The conclusions of that report concern the stability of the storage racks to prevent criticality or other adverse conditions.
Engineered' Confinement Analysis for Supernatant Treatment System The contractor reviewed the analytical work which has been completed for the supernatant treatment system. A variety of techniques have been used for each of the identified barriers to the release of radioactive materials.
In some instances testing was undertaken to gain further insight into the behavior of materials under the imposition of stresses beyond code requirements. The assumption throughout the study is that all code requirements were met.
8608210273 860717 PDR PROJ M-32 PDR
t JUL 17 996 Leland C. Rouse 2
However, the quality assurance program records should be able to indicate the confidence which can be placed in these assumptions..The study also indicates the likely margins inherent in the barriers design, a factor which can also supplement knowledge on the confidence that the total barrier system will, in all credible instances, confine the high-level waste.
Accident Analysis Program The writer and J. Price of SAIC presented information on the commission's program for developing analytical techniques for fuel cycle accidents. The ventilation system for the supernatant treatment system was used as a demonstration example.
Draft SER Review Comments were provided related to accuracy of the Commission's draft safety evaluation report on Volume I.
Status of Cement Solidification System The prime contractor has revamped the cement solidification system. Each of the difficulties encountered during startup and processing of depleted uranyl nitrate hexahydrate has been addressed.
Further processing is planned for a flush out of the uranyl nitrate system. Much of the previous design was subject to cement splash and hardening. The high shear mixer is now designed for remote removal since the Department wants assurance that the cement solidification system can keep pace with the effluent from the supernatant treatment system. About six drums per hour will be produced at the necessary throughput. Very little lag storage is planned at or near the cement solidification operation. A shielded truck with an in-bed conveyor will continually transport the drum to the drum cell facility (the yet-to-be tumulus).
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i Radioactive Waste Treatment Drum Cell Facility l
l A decision is expected very soon from the Department's Deputy Assistant Director for Environment, Safety, and Health on the Finding of No Significant Impact for the actions contemplated in the recently issued environmental l
assessment.
If the decision is in favor of the finding, work will begin soon l
on the drum cell facility. The plan is to construct a base mat which could later serve for conversion to a tumulus, as described in the environmental assessment. Reinforced concrete shield walls will be poured on footings resting on a_ compacted Lavery Till clay covered with a gravel drainage l
layer. A metal frame building, supported by its own steel columns, will be l
constructed to totally enclose the shield walls and support a bridge crane for unloadin Square drums are now planned to minimize void volume (g and stacking drums.and possible consequent subsidence) in the tumulus a l
and enclosure with an engineered cap.
L
r JUL 171986 Leland C. Rouse 3
Assay Techniques for Wastes Contaminated with Transuranics Information was presented on assay techniques. A segmented gamma scanner will be used to ' classify waste' packages in accord with the tables in 10 CFR Part 61 and to obtain data on quantities of radioactive material disposed. A passive neutron system, which relies on delayed neutrons and alpha-neutron reactions in the waste, will be used for higher density containers. The technique will use 78 BF, detectors on all sides of the container with a carbon-hydrogen material to s15w down neutrons for detection.
Detection and estimation of curie content using GM tubes and knowledge of the fission product spectrum will also be used.
A PDP 11/24 computer will be used to analyze and record the data for the above techniques.
Original oigaod by Isoland C. Rouse A. Thomas Clark, Jr.
NRC West Valley Project Manager Advanced Fuel and Spent Fuel Licensing Branch
Enclosures:
As stated DISTRIBUTION:
Project : File..,M-32 i NMSS r/f FCAF r/f ATClark NDavison JRoth, RI RBoyle GBeveridge/SCorne11 LA File n
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- F NAME:ATClark/jl:L Rouse :
DATE:07//G/86 :07//f/86 :
T OFFICIAL RECORD COPY
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ATTACHMENT 1 NRC Visit July 8-11, 1986 Tuesday, July 8
'1: 00;.p;m.
Welcoming Remarks Hannum
'1:15 STS Safety Analysis Incorporating Confinement Lawrence / Gates Study Results 3i45 FRS - Size Reduction with Fuel in Pool Klanian Seismic Analysis 4:15 Adjourn Wednesday, July 9 8:00 FIRAC and Other Accident Analyses Codes Clark 10:00 Discussion / Review NRC Draft SER for SAR Vol. I Clark 12:00 Lunch 11:00 Cemeist Solidification System Status Swenson 3:00 TRU Assay Techniques Valenti Thursday, July 10 8:00 Facility Tour - STS, CTS, Lag Storage (TRU Assay), FRS 10:00 Waste Disposal Plans - 1986 Valenti/Blickwedehl 12:00 Lunch 1:00 HLW Acceptance Developments DOE /NRC Closed Discussion Friday, July 11 8:00 Open Discussion 10:00 Close-Out with DOE Clark /Hannum 11:00 Depart Site
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J ATTACHMENT 2 Meeting Attendees DOE WVNS DAMES & MOORE W. H. Hannum S. Brown W. Gates E. Maestas P. Newsome R. E. Lawrence NRC D. Carl N. H. Davison C. E. Swenson A. T. Clark P. Klanian J. Roth P. Valenti SAIC R. Blickwedehl J. Hamelman A. Stark
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