ML19260B018

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Amend 8 to 790912 Restart Rept Providing Addl Info Re Solid Waste Disposal Sys,Mobile Solidifation Sys,Plant Sheilding & Auxiliary Bldg Ventilation Sys
ML19260B018
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/04/1979
From:
METROPOLITAN EDISON CO.
To:
Shared Package
ML19260B015 List:
References
NUDOCS 7912060349
Download: ML19260B018 (5)


Text

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handle the waste generated from a single operating unit anc TMI-1 operated successfully in the single unit mode in excess of three years during TMI-2 cc_struction. The TMI-2 design utilizec the conservation of the TMI-1 system to provide racwaste treatment capabilities for liquid racwaste generatec from its operation.

Therefore, all TMI-2 liquid racwaste had to be transf erred to TMI-1 for treatment. Therefore isolation of the units will increase the TMI-1 liquid radwaste capability relative to that available during the pre-accident period . The Miscellaneous Waste Evaporation is the primary process equipment used to treat liquic raowaste.

The evaporator has been used successfully in the past for a single unit waste treatment requirements. Because of interferences in TM1-1 causec by the storage of IMI-2 waste waters, the evapora-tion is not currently in use. At the time of startup of TMI-1 (or within the month previous to starting) the evaporation will be shown to be operational or replacement equipment shall be available to supplement evaporation operation.

Although, TMI-1 radwaste processing capabilities are currently limited by the presence of TMI-2 liquid radwaste storea in TMI process vessels, this limitation will be completely re - , by transferring and flushing all TMI-2 waste storea in TMI . .o TMI-2 facilities prior to startup. TMI-2 miscellaneous liquid radwaste will be processed in sys ems installed (or to be installed) in accordance with the recovery effort. The systems include Epicor 2, the submerged demineralizer system and an evaporator / solidification system.

A complete desertption of the TMI-I radtasts treatment system capability is provided in section 7.3.1.. 4 of this report.

7.2.4 Solid Waste Disposal Prior to the accident, TMI-2 radwaste system was completely cepencent on TMI-1 facilities for solid waste processing and disposal of evaporation concentrates, spent resin and compactible trash.

Isolation of the two units will enhance the ability of TMI to process solid radwaste. TMI-2 had installed separate trash compact-ing equipment and will obtain the equipment to solidify liquia anc wet solid waste as part of the recovery program. Thl-1 capabilities are not r quired for the TMI-2 recovery program. THI-1 currently has an opeating trash compactor used exclusively for TMI-1 trash.

Solicification facilities will be available through the use of a contractor for the short term and subsequently through the use of a discussed more thoroughly in Supplement 1, part 2, response to Question 53 and Section 7.3.1.3.

7.2.5 Sanftary Facility Drains By design, sewage and sanitary drains from TMI-2 would join those from IMI-1 at the sewage pumping station and then be treated in a common sewage treatment plant. Operationally, the sewage from the individual unit currently remain separate 1520 220 7-4 Am. 8 7 0120 60 34-9

B. The Auxiliary and Fuel Handling Building Ventilation Systems and the Reactor Building Purge System The auxiliary and fuel handling building ventilation systems and the reactor building purge systems serve primarily to distribute to end exhaust ventilation i air from *.he areas indicated.

7.3.1.3 Selid Waste System  !

7.3.1.3.1 General:

i i

Five general types of waste are produced, processed and shipped from the TMI-1 as solid radioactive waste. These wastes are:

a. Concentrated Liquid Waste (evaporstor bottoms)
b. Used Precoat (spent powdered resin)  ;
c. Spent Resin (bead type) i
d. Dry Compactible Trash I
e. Dry Non-Compactible Trash Dry trash is shpped offsite directly (i.e. , without solidification) I following compaction (to reduce the volume) where possible. TMI-1 has a trash compactor for use with 55 gallon drums dedicated for the exclusive use of the unit. Trash is segregated during collection to insure that TMI-1 and TMI-2 wastes remain separate. Appropriate packaging of dry trash is performed in accordance with applicable shipping and disposal regulations.

Concentrated liquid waste, used precoat, and spent resin will be solidified prior to being shipped offsite for disposal where required by the TMI-1 Technical Specifications and applicable regulations.

Permanently installed plant equipment does not current exist to solidify radwaste.

A two part program has been initiated to solidify these wastes.

For the short term, until the permanent system is available, TMI-1 will use contractor supplied mobile solidification systems. A permanent solidification system using a chemical process developed by Dow Chemical will be installed to replace the mobile systems and is expected to be available by January 1, 1981.

7.3.1.3.2 Mobile Solidification Systems Two specific mobile solidification systems are being considered for use in TMI-1. Niether of the systems considered use urea formaldehyde (UF) as a solidification agent and neither system is subject to the free water problems associated with UF. The systems considered are the Hittman Nuclear and Development Corporation cement in-cask system and a demonstration rystem from Dow Chemical. A Procass Control Program (PCP), approved by the USNRC is required to be available prior to the operation of any radwaste solidification system.

Systems other than the two specifically noted may be considered depending on their ca y ability, availability, and approval of an applicable PCP.

1520 221 7-11a Am. 8

The two mobile systems are described below:

Mobile Dow Solidification System .

I A prototype of a Dow Sclidification System previously used to i demonstrate the process at nuclear plants is available on a rental basis. The system encapsulates tiny droplets of waste material within a hard organic polymer matrix. The equipment consists of i an air driven mixer and fill head anc can be used with 55 gallon l drums.

Prior to beginning actual full scale solidification, the ratios of ,

the chemicals used are determined through laboratory scale trial ,

solidification. The drums are first partially filled with the  ?

appropriate amount of the D0h' binder, a modified vinyl ester resin.

The mixer is placed in the drum and started. Waste is slowly added ,

and thoroughly mixed to achieve an emulsion of the two materials. I Small quantities of two other chemicals are added to the emulsion l to initiate and control the solidification of the binder. r This process may be used to solidify evaporator bottoms and used precoat but not spent resin. Although the system can solidify bead resins, there is insufficient radiation shielding available l

to protect personnel in the vicinity of the process. Complete remote l operation is not possible.  !

The full drum radiation levels expected are:

Evaporator bottoms < 500 mr/hr Used precoat < 2 r/br Spent resin 10-30 ichr Hittman In-Cask Cement Solidification System A solidification system availabla from Hittman uses cement to solidify all three types of waste in a pre-shielded container.

The shielding will be sufficient to protect operating personnel while solidifying spent resin. A disposal liner with an internal mixer is used as the solidification container. The ratios of cement, additives (if required) and waste that will produce a dry product are determined through test solidification in a laboratory in accordance with the PCP.

The quantity of waste to be solidified is pumped into the liner.

(Bead resin may be dewatered to reduce the wast volume.) The mixer is started and cement is added. Mixing is continued until the mixer motor current increases indicating the mixture is beginning to " set". Following visual and tactile verification of solidification the liner and cask are closed and shipped.

1520 2'd d

7-11b Am. 8

Solidification Process Rates '

f DOW Evaporator Bottoms 100 cwft/ day Used Precoat 50 cwft/ day Spent Resin N/A

!!ITTMAN Evaporator Bottoms 200 cwft/ day ,

Used Precoat 100 cwft/ day

  • Spent Resin 100 cwft/ day i i

i Radwaste Production Rate  !

l Evaporator Bottoms 20 cwft/ week  ;

Used Precoat < 1 cwft/ week Spent Resin < 5 cwft/ week Storage Capacity Evaporator Bottoms 1456 cwft Used Precoat 300 cwft Spent Resin 500 cwft Schedule of Doerability Dow Mobile System February 1, 1980 Hittman January 1, 1980*

  • Depending on the approval of the PCP.

The quantity of each of the waste types that require solidification, on site at the time of TMI-1 startup will be less than 50% of the designed storage capacity.

1520 223 7-11c Am. 8

7.3.2 Plant Shielding 7.3.2.1 General:

The purpose of this section is to identify the necessary action to be taken for providing additional shielcing, procr: ures or plant modifications in vital areas and to equipment in which personnel occupancy may be unduly degraced by the large raciar, ion fielas in operating these systems in a post-accident environ'aent.

Systems, components, and areas consicered subject to post-accicent large radiation fields include: decay heat removal, reactor building spray recirculation, make-t; and let-down, wacte gas, Rad Waste Control Center, and Liquid and Gas Waste Panel.

7.3.2.2 Design Review:

In order to determine which areas and systems require additional shield-in or plant modifications, a review of existing design will be completed which will identify and recommend the cor-rective actions needed in vital areas throughout the Unit.

The review will encompass the accessibility and operability of the above stated systems and area in a post-accident environment.

Bases to be used in comparing present design to post-accicent environment. Bases to be used in comparing present design to post-accident radiation levels will be the fission product relacce as describec in Regulatory Guices 1.3 and 1.4. The cesign review will be completed by January 1,1980.

7.3.2.3 Near Term Modifications:

Those near term modifications, identified by the cesign review, will be completed prior to startup of Unit 1.

7.3.2.4 Long Term Modifications:

Over the longer term modifications not completec before startup of Unit I will be completed by January 1,1981.

7.3.3 Auxiliary Building Ventilation System 7.3.3.1 General The Unit-1 Auxiliary Building Ventilation System is combinen with the Fuel Hancling Building Ventilation System prior to filtration 1520 22s 7-12 Am. 8

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