ML20210T009
| ML20210T009 | |
| Person / Time | |
|---|---|
| Issue date: | 02/12/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | Burnham R NUCLEAR PACKAGING, INC. |
| References | |
| NUDOCS 8702180023 | |
| Download: ML20210T009 (3) | |
Text
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Mr. Ronald E. Burnham Manager, Process Systems-February 12, 1987 Nuclear Packaging,-Inc.
1010 South 336th Street
-Federal Way, Washington 98003
Dear Mr. Burnham:
SUBJECT:
REQUEST FOR_ ADDITIONAL INFORMATION ON TP-06-N/P,- REVISION 0 We are currently reviewing Topical Report TP-06-N/P, Revision 0 dated August, 1986 covering the Nuclear Packaging, Inc., Encapsulation System. Our initial review reveals the need for the additional information' indicated in the Enclo-sure.
In' order to complete our review within the currently scheduled time, responses should be received by the NRC by' June 1, 1987. Please advise Charles Nichols at 301-492-7694 if you cannot meet this date.
The reporting.and/or recordkeeping requirements contained in this letter affect
- fewer than ten respondents;;therefore, Office of Management and Budget (OMB) clearance is not required under P.L.96-511.
Sincerely, ORIGligt siti;ED LY IOM Jose A. Calvo, Chief Plant,' Electrical, Instrumentation and Control Systems _ Branch Office of PWR Licensing-B
. Office of Nuclear. Reactor Regulation
Enclosures:
As stated Distribution eCentre M U e-D. Crutchfield NRC PDR R. Emch PEICSB Rdg. File J. Calvo F. Miraglia J. Wermiel T. Speis-C. Miller
-G. Lainas J. Minns C.E. Rossi C. Nichols H. Berkow f
fl1L PEICSB ~Cp.M P CB PEICSB CNichols:sr JWermiel JCalvo 2/p/87 2//2/87 2//?]87 8702180023 870212
{DR TOPRP ENVNPI PDR
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'l LICENSING REVIEW OVESTIONS ON TOPICAL REPORT TP-06,B/P, REVISION 0 NUCLEAR PACKAGING, INC. ENCAPSt,LATION SYSTEM Provide a revised version (Revision 1) of the subject topical report including all the desired changes identified with vertical lines in the margin.
Revi-sion 1 should incorporate all of the responses to the following review questions on the Revision 0 report:
1.
Describe the different types and characteristics of solid waste that may be encapsulated and those that may not, e.g., salts, powders, cloth, paper, tools, cartridge filters, structural materials, moisture content, combustibles.
~
,2.
InSection2.1.1,describethemeansfordeterminingthatthesettimeis within specified limits, and actions to be taken if it is not within thdse limits.
3.
In Section 2.2, clarify the source of the metered flow (drum and pump P-2 or manual valve V-2) and the means for metering the flow including provi-sions for assuring complete transfer of any predetermined volumes. Clar-ify the means for adding Envirostone to the cement hopper including pro-visions for assuring complete transfer. Describe any means provided for vibrating the hopper.
4.
In Section 2.3, clarify step 27 including the meaning of " closing a motor."
l' 5.
In Section 2.4, describe provisions for determining appropriate proportions of Envirostone and water considering the different types and characteris-tics of solid wastes to be processed. Clarify how the binder surrounds and encapsulates the solid waste without mixing with it, but at the same time the " low viscosity slurry fills all voids around the radioactive material." Provide the meaning of "PNS."
Describe the possible effects on waste fonn characteristics and integrity due to lengthy interruptions in the addition of Envirostone slurry to a liner. Describe how this addi-tion process is controlled to minimize any adverse effects on the waste form due to interruptions.
'i 6.
In Section 2.5, provide the criteria to be used to accept a liner after completion of the fill process and describe actions to be taken if the criteria are not met. Describe any tests that have been performed or other rationale to demonstrate that the NuPac fillport provides a void-free distribution of Envirostone in the annular region around a basket of waste. Describe any hot-spot surveys to be perfonned to verify the absence of voids in this region. Clarify the discrepancy between the report provided in Appendix A and the reference to it provided in Sec-tions 2.5.1 and 8.3.
Provide the status of the NRC review and approval of the U.S. Gypsum Company topical report on the stability (or compliance)
N testing of the Envirostone Gypsum Cement solidification medium. Clarify J
m
, that the information provided in Sections 2.5.2 through 2.5.7 was obtained Resolve the discrepancies between from the U.S. Gypsum topical report.
the information provided in these' sections and the information contained in the referenced report provided in Appendix A.
In Section 4.1, provide a sketch of a recommended system layout showing 7.
sizes of skids and components, the distance from each other, the location of the control and power panel, and shielding. Describe how this layout minimizes radiation exposure.
In Section 4.2, provide a more-detailed discussion of the provisions.for 8.
controlling radiation exposure, including a breakdown by task and time in the radiation field for the processing of each of the various types of In this discussion, address the significance of the type and solid waste.
size of the liner. Provide support for any comparisons of exposures from~
one type of waste to another. Provide. justification for use of the Apparent Reduction Potential (ARP) of NUREG/CR-0446 as a basis for evalua-3, Clarify that the ARP " flag level" for ting actions to reduce exposures.
action is 1.0 according to Appendix B, Page 147, of NUREG/CR-0446.
In Section 5.0, provide a discussion of radiation safety, fire and indus-9.
trial safety, engineering safety features, and special monitors and alanns.
In Section 7.14, clarify which company President is meant.
10.
Provide a description of the types, sizes and suppliers of liners and 11.
baskets, including a drawing of a liner with basket in place showing the thickness of the annulus between basket and liner. Provide justifica-tion for any credit taken for shielding by the liner and the annulus l
region.
Provide a description of the process of loading of waste into the liner 12.
and attaching the fillport to the loaded liner, clarifying the tasks to be perfonned by the NuPac system operator and other pertinent tasks by plant personnel. Describe shielding provided around and above a liner to minimize exposure during fillport attachment and level switch adjustments.
Provide a description of the interface requirements between the NuPac 13.
system and the plant, including not only physical interfaces such as qlec-tricity, water, and drains, but also services such as waste classifica-tion, labeling, decontamination of liner surfaces, and shipping.
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