Topical Rept Evaluation of CNSI-DW-11118-01-P, Chem-Nuclear Sys,Inc Dewatering Containers. Rept Acceptable for Referencing License Applications for LWRs| ML20127D028 |
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| Issue date: |
06/11/1985 |
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| From: |
Office of Nuclear Reactor Regulation |
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| To: |
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| Shared Package |
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| ML20127D019 |
List: |
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| References |
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| NUDOCS 8506240096 |
| Download: ML20127D028 (7) |
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Category:TEXT-SAFETY REPORT
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[Table view]Some use of "" in your query was not closed by a matching "".
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1994-08-25
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Text
.. ._ __. _ _ _ _ _ _ . . -____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
SAFETY EVALUATION REPORT Report Number: CNSI-DW11118-01-P(CNSI-11118-01-P)
Report
Title:
CNSI Dewatering Containers Originating Organization: Chem-Nuclear Systems, Inc. Columbia, SC Reviewed by: Meteorology and Effluent Treatment Branch, DSI, NRR
1.0 INTRODUCTION
The Chem-Nuclear Dewatering System (the Chem-Nuclear System) utilizes transportable and disposable steel, polyethylene, or fiberglass containers to dewater radioactive spent bead and powdered resins, and filter precoats (i.e.,
diatomaceous earths, Celite, Fibra-cel). The dewatering process uses an air-driven positive displacement pump to obtain a continuous suction on a waste container. This suction removes pumpable liquid to a predetermined end point in accordance with the Ches-Nuclear process control program to meet the free standing liquid criteria set forth in Section 61. 56(a)(3) of 10 CFR Part
- 61. Vacuum gauges are provided at each waste inlet connection and manifold.
The water removed from a waste container is returned to the user's liquid radwaste system.
The review of the Chee-Nuclear System, which was conducted in accordance with Section 11.4 of the Standard Review Plan (SRP), included'the waste container internal design drawings, descriptive inferination on the dewatering operation, 8506240096 850611 TOPRP ENVC
{DR
2 equipment description, process control program, and quality assurance program.
The dewatering process treats " wet" radioactive waste to seet requirements in NRC Branch Technical Position. ETSB 11-3, Revision 2 in SRP Section 11.4. The process is not intended to meet the waste stability form or classification requirements in 10 CFR Part 61. > '
- l<
Chem-Nuclear submitted separate topical reports on High Integrity Containers for NRC review and approval. In these reviews by the MSS staff, the structural integrity of the Chem-Nuclear containers is being evaluated to ensure long-term isolation of low-level radioactive waste from the soil environment.
1 2.0 EVALUATION i
The design and operation of the Chem-Nuclear System are described in detail in the Chem-Nuclear Topical Report, CNSI-11118-01-P and in the Chem-Nuclear responses dated April 15,1985 to the NRC licensing review questions. In the staff's evaluation of the Cheta-Nuclear System, the staff considered:
(1) The process control program to assure complete dewatering of " wet" solid radwaste.
(2) Design provisions incorporated in the equipment'and system design to reduce leakage and (ontrol and monitor releases of radioactive effluents to the environment.
(3) The quality assurance prograni for the. design, fabrication and testing of the system.
t i (4) Typical interfaces with the reactor plant. ,
I l
i
3 J
(5) Radiation protection design features.
The system consists of a dewatering waste container, a dewatering pump, an off-gas collection unit, a container level indicator-controller, a control valve, and interconnecting piping. '
[
s*
After " wet" radwaste from the user's plant is charged into a Chem-Nuclear waste container, dewatering is akhteved with continuous suction on a waste r
container provided by the dewat ring pump . Varioustyphsandnumbers'of ',,
' ^
filters are used within the waste container in different configurations to l '
retain spent resin and filter precoat materials. Water removed from the waste '
/ /
I container is returned to the user's liquid radwaste ' system. j t
t' The pump is operated for given time intervals in accordance'with the ,
l f
Chem-Nuclear proced, control program. Usually, the cycle is eight hours of '
,y , ,
pumping followed by e'ight hours of standing. The purpihgjmay range from three to twelve cycles depending upon type of wastes and waste containers. ; ,
The waste container is considered dewatered when the volume of collectable liquid meets the acceptance criteria in the Chem-Nuclear process control program. !
+-i f! '
The topical report describes Chem-Nuclear generic Process Control Programs I a
(PCPs) for dewatering spent bead resin and filter precoats for dewatering to "
ensure that the dewatered waste containers meet the free standing liquid criteria set forth in Section 61.56(a)(3Yof 10 CFR Part 61. The PCPs are t
developed based on the <actual test results on drainable and pumpable liquid I , a
' I s ( /
1, ,s .
( . t
?
r -$
d
... . 4 obtained from dewatering polyethylene, and steel containers and from the n
subsequent road tests on dewatered waste containers.
1
/
The staff reviewed the Chem-Nuclear dewatering test procedures, detailed dewatering erating procedures, and acceptance criteria specified in the Chem-Nuclear PCPs. The staff finds the Chem-Nuclear acceptance criteria and
. i ,.
dewatedng' test resul'ts thet the free standing liquid criteria in 10 CFR Part 61 and NRC _ Branch Technical Position ETSB 11-3, Revision 2 and, therefore, the
/i ; y v staff finds the Chem-Nuclear PCPs to be acceptable.
No airborne or liquid radwastes are released to the environment from the Cheu-Nuclear dewatering operation. The dewatered liquid radwastes are routed to the user's liquid radwaste system and the waste container fillhead and seal pan are connected to the user's monitored plant ventilation system. The pressurized hoses utilized in the dewatering operation are hydrotested up to 225 psig and hoses tha~ '.re under continuous pressure are steel reinforced and of the non-collapsifle t type.
The Chem-Nuclear System is designed to prevent uncontrolled releases of radioattive$aaterials by monitoring liquid levels in the waste container by a level indicator and controller. During the waste filling operation, the operstor is required to be stationed near the control panel cnd visually monitor the' as.te' transfer process. Curbs or other means to contain ina6Nrtent' spills and overflows will be provided by the user with floor
'_ drains routed to the user's liquid radwaste collection systems.
t r
, e y #
- k o l
,! ,d ,,
f i f' an
5 The consequences of a waste dewatering container failure releasing radioactive materials to a potable water supply is site dependent and will be evaluated for individual license applications. The staff finds the Chem-Nuclear dewatering process and waste container design meet the requirement of Section
Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
The design, procurement, fabrication, testing and operation of the Chem-Nuclear System is accomplished under prescribed quality assurance '
requirements which conform, to the extent practicable, with the guidelines ;
provided in Regulatory Guide 1.143 " Design Guidance for Radioactive Waste Management Systems Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants." The quality assurance program defines and controls those elements of Chem-Nuclear and their suppliers' perfonnance which affect the quality of the Chem-Nuclear System.
Layout diagrams for a typical Chem-Nuclear System installation show an isolated and shielded location for the system control panel. The design and .
arrangement of the Chem-Nuclear System components are based on maintaining the operator radiation exposure as low as is reasonably achievable. The topical report provides a list of specific design and operating features which were incorporated to minimize personnel radiation exposure. All active components are located so they can be easily accessed for maintenance. All pumps, valves and piping can be flushed prior to inspection and maintenance. The staff finds that Chem-Nuclear has adequately identified interface information and requirements which users should provide.
l l . . _ --
P 6
Upon completion of the staff review by NHSS of the Chem-Nuclear topical e reports on High Integrity Containers, a separate Safety Evaluation Report will L be provided to supplement this evaluation. l f
3.0 CONCLUSION
Based on the foregoing evaluation, the staff finds the Chem-Nuclear Topical Report, CNSI-DN-1118-01-P to be acceptable, f The bases for our acceptance is our conclusion that the Chem-Nuclear Dewatering System is designed and can be operated in accordance with current t guidance of applicable regulatory guides, standard review plans, branch technical positions, and Federal regulations.
The capability of the plant radioactive waste treatment systems to meet the i requirements of Appendix I to 10 CFR Part 50 with the Chem-Nuclear System in operation is site dependent and will be evaluated for individual license applications. In addition, the packaging and shipping of all processed wastes including waste classification and waste form requirements in accordance with the applicable sections of 10 CFR Parts 61 and 71, and 49 CFR Parts 170-178, will be detemined for individual license applications. The consequences of a potential waste container failure releasing radioactive materials to a potable water supply is also site dependent and will be evaluated for individual license applications. l 1
' + - - ,-. - - - - o -" w "wr T"* * '**'~-*
.- 7
, . The staff concludes that the Chem-Nuclear Topical Report is acceptable for reference in future license applications for light water reactors. Any application incorporating this report by reference should include the
. following infonnation:
(1) Any exceptions or deviations from the Chem-Nuclear Topical Report dated December 1983, (2) Interfaces between the plant and the Chem-Nuclear System.
(3) Location and arrangement drawings of the Chem-Nuclear System in the plant including curbs or other means to contain inadvertent spills and overflows.
(4) The waste classification program to demonstrate that the solid waste product is classified in accordance with 10 CFR 61 Section 61.55 and NRC Branch Technical Position on Wastr; Classification, (5) Description of the solid waste product container to be used, (6) The capability of the plant radioactive waste treatment system to meet the requirements of Appendix I tes CFR Part 50 with the Chem-Nuclear System in operation.
_