ML20215N392
| ML20215N392 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215N376 | List: |
| References | |
| NUDOCS 8611050333 | |
| Download: ML20215N392 (6) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION Report Number:
STD-R-05-011, Revision 2 Report
Title:
Mobile Incontainer Dewatering and Solidification System (MDSS)
Originatina Westinghouse-Hittman Nuclear, Inc.,
Organization Columbia, MD Reviewed By:
(1) EG8G Idaho, Inc.
(2) Plant Systems Branch, Division of PWR Licensing.- A
1.0 INTRODUCTION
On December 18, 1985 Westinghouse-Hittman Nuclear, Inc. (WHN) submitted for NRC review and approval their licensing topical report STD-R-05-011. " Mobile Incontainer Dewatering and Solidification System (MDSS)." This document was reviewed by EG&G Idaho, Inc. and questions were submitted to WHN in June of 1986. The topical report was revised and resubmitted in July, and again in October,1986; the revision number was changed but the publication date remained July. This safety evaluation is based on the revised topical and the review of that document by EG&G.
This evaluation addresses the systems and operations issues. The acceptability of the form of the solidified waste is being evaluated by the Office of Nuclear Materials Safety and Safeguards.
The WHN report addresses two separate methods of processing wet radioactive waste for shipment to a disposal site. The wastes may either be solidified or simply dewatered (dried).
In either case the processing is done in the container that will be shipped and disposed.
For dewatering, WHN uses a special porous plastic pipe with pore sizes no greater than 5 microns. This permits the dewatering of a wide range of wastes, including powdered resins in the container and without centrifuging.
ClassAwastes(thosewithlittleradioactivity)maybedewateredinsteel containers while high integrity containers (HICs) are required for Class 8 or C wastes.
In either case the operating limits are that the pH must be between 4 and 11 and the temperature must not exceed 140 degrees Fahrenheit. After the initial dewatering operation, the waste is allowed to settle for a day and dewatered again. This is repeated until the water content criteria (0.5% in steel containers and 1% in HICsl are met.
For solidification, WHN uses Portland Type I cement as a solidification agent. The amount of cement used and the other additives depend on the waste being processed. WHN has submitted test data to demonstrate compliance with the waste form criteria for a variety of wet wastes and the quantities are detailed in WHN report STD-R-05-006. The wastes are mixed with the cement and additives in a large steel liner, mixed with disposable plestic mixing blades, and allowed to solidify.
8611050333 861031 DR TOPRP EMVWHIT PDR
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' 2.0 EVALUATION The WHN system and-its operation are described in detail in the topical report.
In evaluating the WHN system the staff has considered:
(1) The system design criteria and design bases.
(2) The process capability compared to the inplant waste volumes expected during nonnal light water reactor (LWR) operations, including anticipated operational occurrences.
(3) The quality group clas.sification and quality assurance program for the design, fabrication and testing of the system.
(4) Design provisions incorporated in the equipment and system to reduce leakage and to control and monitor releases of radioactive effluents to the environment.
(5) Process control program to assure complete solidification of " wet" solid radwaste.
(6) Radiation protection design features to assure that occupational radiation exposures are maintained as low as is reasonably achievable (ALARA).
(7) The fire and explosive hazards associated with the flamable materials i
used in the WHN system.
2.1 Design Criteria The design acceptance criteria for solid radwaste systems are specified in Section 11.4 of the SRP and Regulatory Guide 1.143. They are based on meeting the relevant requirements of (1) General Design Criteria (GDC) 60, 61, 63 and 64 of Appendix A to 10 CFR Part 50, as they relate to the radioactive waste management systems being designed to control releases of radioactivity to the environment, and to monitor radiation levels and leakage in and from the systems, and (2) Sections 50.34a and 50.36a of 10 CFR Part 50 as they relate to the provisions of assurance that the releases of radioactive material to unrestricted areas are kept "as low as is reasonably achievable".
The design bases of the WHN system relating to the processing rate and capacity were derived from the expected annual volumes of wet radioactive wastes from typical 3400 megawatt thermal (MWt) LWR plants. The wet wastes include powdered resin, bead resin, oil, boric acid liquid waste, filter sludge and evaporator bottoms.
The WHN system is designed to handle the expected quantities with 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week operation so' higher quantities could be handled with additional operation.
The WHN systen need not produce additional direct releases of either liquids or gases to the environment. Any releases that do occur shall be controlled and monitored so the total release from the plant do not exceed ALARA requirements.
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- On the basis of the foregoing evaluation, the staff finds that the WHN system design criteria and design bases meet the requirements of Section 50.34a and 10.36 of 10 CFR Part 50, and GDC 60, 61, 63 and 64 of Appendix A to 10 CFR Part 50.
2.2 Radiation Protection
' The WHN system incorporates several features which are designed tn keep personnel radiation doses ALARA. The most important are that the system is designed to be operated remotely and that the control panels are located as far as practical from the radioactive materf al being processed. Also containers being processed are shielded. While some manual operations remain, the expected doses are only about 35 mrems from solidification and 20 mrems from a dewatering operation per batch. The WHN operators are subject to the health physics controls and protective measures of the plant. Therefore, the staff finds the radiation protection provisions acceptable.
2.3 Fire Protection and Spill Control The WHN system is designed to maintain relatively low temperatures during operations and the solidification materials present minimal fire control problems. Any fire in the electrical equipment would be readily extinguished i
and would not release significant amounts of radioactive material. A HIC-containing radwaste could burn enough to cause a spill but the spill would put 3
i out the fire. Therefore, the staff finds the system acceptable with normal fire detection and extinguishing provisions.
j The WHN system is designed to minimize spills but the possibility cannot be completely eliminated. To ensure that a possible spill would not have unacceptable radiological consequences, WHN has analyzed a range of accidents of this sort. These include (1) rupture of a liner, (2) rupture of a transfer hose, (3) rupture of the vacuum receiver tank, and (4) failure of various pieces of equipment.
In no case did the calculated airborne radioactivity exceed the MPC values of 10 CFR Part 20, Appendix B.
Furthermore, the liquid volumes are small enough to be controlled with normal measures. Therefore, the staff finds the spill control measures acceptable.
2.4 Process Control Program (PCP)
The WHN topical report includes a standard Process Control Program as an appendix. The staff has reviewed this PCP and found it acceptable for the operation of the WHN system.
It is suitable for incorporation into the plant PCP by reference.
2.5 Interface Requirements The principal interface requirements for the WHN system are detailed in Table 4-2 of the topical report. These include floor space, a crane, service air, service water, electrical power (480 V AC), floor drains, waste transfer lines and shielding.
It is noted elsewhere in the report that the plant operator is also expected to provide health physics protection and control measures; this should include control and monitoring of airborne radioactivity and curbs or the like for control of spilled liquids.
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3.0 CONCLUSION
On the basis of the foregoing evaluation and the EGAG Technical Evaluation Report (EGG-PHY-7335), the staff finds the WHN topical report, STD-R-05-011, Revision 2, " Mobile Incontainer Dewatering and Solidification System (MDSS)",
dated July 1986 to be acceptable for referencing in future license applications or amendments for light water reactors.
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Mr. R. J. Leduc J l
Should our criteria or regulations change such that our conclusions as to the acceptability of the report are invalid, Westinghouse-Hittman and/or applicants referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the topical report without revision of their respective documentation.
Sincerely, 6PlRIhni sianed by:
Charles E. Rossi, Assistant Director Division of PWR Licensing - A
Enclosure:
~
As stated DISTRIBUTION Central Files PSB R/F PSB Subject File A/D R/F R. Emch J. Milhoan T. Quay C. Willis C. Nichols J. Lee J. Greeves G. Lainas F. Miraglia R. Bernero J. Calvo L. Hulman H. Thompson i
R. Diggs, LFMB B. Clayton PDR DPLA RF 1
- See previous concurrence
- 0FC
- PWR A:PSB
- PWR-A:PSB
- PWR-A:PSB
- PWR-B:PEICSB:B PSB
- PWR NAME :CWillis*
- T0uay*
- JMilhoan*
- JCalvo /4'l :LH n
__...:_______ ____:-_.-_-____..:....________:....______.:______..____:.. _____....g:...._______
.i0 ATE :10/27/86
- 10/27/86-
- 10/27/86
- 10/29/86
- 104t3/86
- 10/K/J86 OFFICIAL RECORD COPY
OCT 3186E Mr. R. J. Leduc 7-Should our criteria or regulations change such that our conclusions as to the acceptability of the report are invalid, Westinghouse-Hittman and/or applicants referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective-applicability of the topical report without revision of their respective documentation.
Sincerely, 6rltinai signed bys Charles E. Rossi, Assistant Director Division of PWR Licensing - A
Enclosure:
As stated DISTRIBUTION Central Files PSB R/F PSB Subject File A/D R/F R. Emch J. Milhoan T. Quay C. Willis C. Nichols J. Lee J. Greeves G. Lainas F.~Miraglia R. Bernero J. Calvo L. Hulman H. Thompson R. Diggs, LFMB B. Clayton PDR DPLA RF OFC :PWR-A:PSB
- PWR-A:PSB
- PWR PSB
- PWR-A:AD
_____:.____....__ : _____ g)p.
NAME :CWillis
- TQuay 1
an
- CERossi DATE :10/27/86
- 10/27/86
- 1 /27/86
- 10/ /86 OFFICIAL RECORD COPY