ML19207B340
| ML19207B340 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/17/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19207B339 | List: |
| References | |
| NUDOCS 7908240459 | |
| Download: ML19207B340 (8) | |
Text
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Connecticut Yankee Process Control Program
] $5'{
7008240 f h
PROCESS CONTROL PROGRAti PURPOSi The pu" pose of the Process Control Program (PCP) is to ensure that the radwaste liquid solidification system is operated to produce a final product that contains no free water and results in completely solidified waste.
Interfacing this effort will be batch sampling of the liquid radwaste to determine:
1) radioactivity content and 2) mixture ratio of concrete to waste liquid that ensures complete solidification with no free water.
The liquid radioactive waste that requires solidification shall be processed as described in the PCP and as directed by the procedures in the Plant Operating Manual.
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Section 1 - LIQUID WASTE SYSTEM 1.1 Function The liquid waste system treats and disposes of aerated radioactive liquids and steam generator blowdown. This system accepts liquid from steam generator blowdown, contaminated and uncontaminated drains and processes these liquids for drumming or discharge to service water.
This processing consists of filtration, ion exchange, holdup, evaporation, dilution and drumming.
Heat tracing is provided on systems that are expected to pass liquids with a twelve percent (by weight) boric acid concentration.
These systems are heat traced to 170 F to prevent the boric acid from solidifying.
SUMMARY
DESCRIPTION Following concentration of the waste liquid (to ~12 percent boric acid) in the evaporator system, the waste concentrated bottoms cre sampled and then transferred to the drunming station where the bottoms are drummed for disposal.
Boron recovery system bottoms are handled in the same manner, if drumming is required.
The drumming process is perfonned manually by mixing, in a drum, approximately 30 gallons of waste liquid with four 90 lb. bags of concrete, and by rolling each drum for 15 minutes.
After a set up time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, each drum is inspected for free water.
Concrete is added to any drum containing excess water.
A program entailing the sampling frequency of bottoms and labor-atory determinations of concrete to bottoms ratios will be developed.
Until that time a ratio of 1.4 parts of concrete to 1.0 part of water will continue to be used in conjunction with visual inspection.
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1.2 N '.' (. w r J O:1S, T.l M ITAT I OllS, hiiD CONTI
- nent following:
1.
Steam Generator nlowof f Tank Cooler 2.
Haste Evaporator Distillate Cooler 3.
Haste Evalorator Ectto ns cooler ts.
Mechanical seal and cooling water jacket for the Waste Evaporator,Reboiler Pump and Waste Evaporator Dottoms Pump.
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c.
Service C. t. c. r t.o provide cooling wat er for the St, cam Gme2 at or n]u rof f Tank Conacnsers
.a nd 1.he Wast.c Evapora" or Overbecd Condenser.
d.
Control Air t_ o perform various control functions throughout the system.
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ent. il a t ion and Purge system to provide the
'r e.
following:
1.
Over pressure relief protection for the Steam Generator Blowoff Tank.
2.
Vent path for the removal of any gases trapped in the top of the Waste Evaporator Distillate Filter.
3.
A constant or automatic thermostatic-type vent for:
a)
Steam Generator Blowoff Tank Condensers b)
Aerated Drain Tank c)
Aerated Drain Holdup Tank d)
Waste Evaporator Overhead Condens'er c)
Waste Evaporator Distillate Tank f)
Waste Test Tanks 1.2.2.2 Systems dependent on the Liquid Waste System for operation:
a.
Waste Disposal System 1.2.3 Precaution,s and Limitations..,
V
/L 1_2.3.1 All liquid collected and stored in the tankage of the Waste Disposal System must be sampled for radioactivity and solids concentration prior to.
discharge to the environment.
1.2.3.2 Discharge of any liquid from the Waste Disposal System is authorized only by issuance of a Liquid Radioactive Release Pennit.
1.2.3.3 Liquids processed by the Waste Evaporator are to be processed in accordance with the run sheet issued by the Chemistry Department.
1.2.3.4 Radiation IcVels of drums containing radioactive waste should not exceed established limits (200 mr/hr contact, 10 mr/hr at 1 meter).
6 PDDR DIElkkL -
SECTION Z - PURIFICATION SYSTEM 1.1 General Description The purification system functions to remove impurities from the following areas:
- The reactor coolant system during plant operation
- The reactor coolant ofstem during plant shutdown and depressurization
- The volume control tank and refueling water storage tank water when necessary
- The reactor cavity water during refueling operations
- The spent fuel pit water when necessary The purification system also provides make-up water to the spent fuel pit and the refueling water storage tank.
The purification system components are located outside of the reactor containment.
The system operates at low pressures and temperatures.
Systems Include:
Reactor Coolant System Purification This system operates to reduce fouling of heat transfer surfaces by maintaining reactor coolant purity.
Purification is accomplished by diverting the letdown flow through one or two mixed bed demineralizers for removal of ionic isotopes.
The demineralizers can be operated either in parallel or series.
The demineralizer effluent is then passed through the reactor coolant filter for removal of resin fines and other insoluble materials.
A deborating demineralizer is also provided for removal of boron from the reactor coolant.
This demineralizer may be placed in operation when the reactor coolant system boron concentration is approximately 30 ppm or less.
The demineralizers normally operate at a temperature of 115 F.
Ilowever, if during operation, the temperature of the incoming liq'iid exceeds 140 F, the flow is automatically bypassed around the demineralizers and the condition is alarmed in the main control room.
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The demineralizer resin b2ds are designed to reduce the concentration of ionic isotopes in the purification stream by a minimum factor of 10, except for Cs '37, Y-90, Y-91 and MD-99, for which no remov 1 is assumed.
This design criterion provides satisfactory performance for the primary plant operation.
Volume Control Tank and Refueling Water Storage Tank Water purification The volume control tank and refueling water storage tank water can be subjected to the same purification cycle as that described for the reactor coolant letdown.
This is accomplished by using the purification pump to cycle the liquid from one tank, through a mixed bed demineralizer and reactor coolant filter, and back to the tank.
The piping arrangement permits simultaneous purification of the reactor coolant letdown and either the volume control tank or refueling water storage tank water.
- However, one of the two streams must bypass the reactor coolant filter to prevent intermixing at the filter.
- 2. 2 Spent Resin Hand)ing There are three mixed bed type purification demineralizers.