ML20135F923

SER of Rev 1 to Topical Rept TP-02-P, Nuclear Packaging,Inc Dewatering Sys. Rept Acceptable for Referencing in LWR License Applications

ML20135F923
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Issue date:	09/06/1985
From:	Office of Nuclear Reactor Regulation
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ML20135F917	List: ML20135F914 ML20135F923
References
NUDOCS 8509180019
Download: ML20135F923 (8)

Text

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4 ENCLOSURE l

SAFETY EVALUATION REPORT

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j Report Number: TP-02-P, Rev. 1 Report

Title:

Nuclear Packaging Dewatering System Originating Organization: Nuclear Packaging, Inc., Federal Way, WA Reviewed by: Meteorology and Effluent Treatment Branch, DSI, NRR i

1.0 INTRODUCTION

TheNuclearPackagingDewateringSystem(theNUPACSystem)utilizesdewatering l _

equipment and disposable waste containers to dewater radioactive spent bead and powdered resins, and filter precoats. The dewatering process uses an air-driven positive displacement pump to obtain a continuous suction on a waste container to remove the bulk of free water. Then, the air blower recirculates air through the waste container and water separator to facilitate drying of the resin. These processes remove pumpable liquid from the waste container to a predetermined end point in accordance with the NUPAC process control program to meet the free standing liquid criteria set forth in Section 61,56(a)(3)of10CFRPart61. Vacuum gauges are provided at each waste outlet connection and manifold. The water removed from a waste container is

, returned to the user's liquid radwaste system.

3 The review of the NUPAC System, which was conducted in accordance with Section 11.4 of the Standard Review Plan (SRP), included the waste container internal design drawings, descriptive information on the dewaterfng operation, 8509180019 850906 DR TOPRPEPfVffy p

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equipment description, process control program, and qualtiy assurance program. The dewatering process treats " wet" radioactive waste to meet 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.

Nuclear Packaging submitted separate topical reports on High Integrity Containers for NRC review and approval. In these reviews by the HMSS staff, the structural integrity of the NUPAC containers is being evaluated to ensure long-tern isolation of low-level radioactive waste from the soil environment.

2.0 EVALUATION The design and operation of the NUPAC System are described in detail in the NUPAC Topical Report, TP-02-P, Rev. O and Rev. 1 dated August 6, 1984 and June 28, 1985 respectively. In the staff's evaluation of the NUPAC System, the staff considered:

(1) The process control program to assure complete dewatering of " wet" solid I

radwaste. , ,

(2) Design provisions incorporated in the equipment and system design to reduce leakage and control and monitor releases of ' radioactive effluents to the environment.

I (3) The quality assurance program for the design, fabrication and testing of the system.

(4) Typical interfaces with the reactor plant.

(5) l!aste container internal design.

(6) Provisions to control potential exothermic reaction in dewatering ion exchange resin.

(7) Radiation protection design features.

The NUPAC System consists of a dewatering waste container, a dewatering pump, an off-gas vent unit, a container level indicator, a waste fill head, a water separator with water chiller unit, an air blower, a relative humidity instrument, a control panel, and interconnecting piping and valves.

After " wet" radwaste from the user's plant is charged into a NUPAC waste container, dewatering is achieved with continuous suction on a waste container provided by the dewatering pump. The residual free water in the waste container is removed by recirculation of drying air provided by the air blower.

Various types and numbers of filters are used within the waste container in different configurations to retain spent resin and filter precoat materials.

Water removed from the waste container is retur,ned to the user's liquid radwaste system.

The dewatering pump is operated for given time intervals in accordance with the NUPAC process control program. The pumping time may range from eight to

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l sixteen hours depending upon type of wastes and waste containers. After most of the free water in the waste container has been removed, drying air is' continuously recirculated in a loop from the air blower to the waste container through the water separator to remove any residual free water in the waste

. container. The NUPAC System is provided with temperature instrumentation which is interlocked to automatically shut down the dewatering process on high air temperature due to potential exothermic reaction in dewatering ion exchange resin.

I The waste container is considered dewatered when the volume of collectable liquid and relative humidity in the recirculating drying air meet the acceptance criteria specified in the NUPAC process control program. A relative humidity instrument and monitor are provided to remotely and continuously monitor the waste container outlet air. This instrument is used to establish positive end point to the dewatering process.

The topical report describes NUPAC generic Process Control Programs (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)(3) of 10 CFR Part 61., The PCPs are developed based on the actual test results on drainable liquid obtained from dewatering waste

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containers and from the subsequent road tests on dewatered waste containers.

The staff reviewed the NUPAC dewatering test procedures and its results, detailed dewatering operating and maintenance procedures, and acceptance criteria described in the topical report. The staff finds the NUPAC acceptance criteria and dewatering test results meet the free standing liquid criteria in 10 CFR Part 61 and NRC Branch Technical Position ETSB 11-3, Rev. 2 and therefore, the staff finds the NUPAC PCPs to be acceptable.

No airborne or liquid radwastes are released to the environment from the NUPAC i

dewatering operation. The dewatered liquid radwastes are routed to the user's liquid radwaste system and resin drying air is vented to the user's off-gas system. The NUPAC System is designed to prevent uncontrolled releases of radio' active materials by monitoring liquid levels in the waste container by a level indicator. During the waste filling operation, the operator is required to be stationed near the control panel and visually monitor the waste transfer process observing the video monitor and the radiation monitor provided. Curbs or other means to contain inadvertent spills and overflows will be provided by the user with floor drains routed to the user's liquid radwaste collection systems.

The consequences of a waste dewatering containe,r failure releasing radioactive materials to a potable water supply is site dependent and will be evaluated for individual license applications. The staff finds th'e NUPAC dewatering process and waste container design meet the requirement of Section 20.106 of 10 CFR Part 20, Section 50.34a of 10 CFR Part 50, and General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

The design, procurement, fabrication, testing and operation of the NUPAC 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 NUPAC and their suppliers' performance which affect the quality of the NUPAC System.

The design and arrangement of the NUPAC 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.

i The staff also finds that NUPAC has adequately identified interface information and requirements which users should provide.

Upon completion of the staff revicw by NHSS of the NU?AC topical reports on High Integrity Containers, a separate Safety Evaluation" Report will be provided to supplement this evaluation.

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3.0 CONCLUSION

Based on the foregoing evaluation, the staff finds the NUPAC Topical Report, TP-02-P, Rev. 1, to be acceptable.

The bases for our acceptance is our conclusion that the NUPAC Dewatering System is designed and can be operated in accordance with current 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 requirements of Appendix I to 10 CFR Part 50 with the NUPAC 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 in accordance with the applicable sections of 10 CFR Parts 61 and 71, and 49 CFR Parts 170-178, will be determined 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 oe evaluated for individual license applications. , ,

The staff concludes that the HUPAC Topical Report is acciptable for reference in future license applications for light water reactors. Any application incorporating this report by reference should include the following information:

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- 8-(1) An) exceptions or deviations from the NUPAC Topical Report, Rev. 1, dated June 19S5.

(2) Interfaces between the plant and the NUPAC System.

(3) Location ano arrangement drawings of the NUPAC System in the plant incitding 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 Part 61, Section 61.55 and NRC Branch Technical Position on Waste 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 to CFR Part 50 with the NUPAC System in operation. .

(7) The plant site information on potable water supply.

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