ML20214G675
| ML20214G675 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/06/1971 |
| From: | Jay Collins US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0144, CON-WNP-144 NUDOCS 8605220393 | |
| Download: ML20214G675 (4) | |
Text
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December 6, 1971 6
3h V. Stt'lo, Chief, BWR Branch Nc. 4, DP.L TERU:
B. Grimes, Chief, Radiological Safety Branch, DEL REV1 W OF TEE RADWASTE SYSTES FROPOSED FOR BAEFORD 50. 2, WFPS The redraste treatment systems described in the PSAR for Banford No. 2 have been reviewed and the following commenta and questions are offered.
Es general the applicant has failed to furnish sufficient information for us to complete our evaluation, In view of this deficiency we are unable to state whether the proposed systems are adequate to maintain releases at the lowest levels practicable and will function as described.
Specific comments are as follows:
1.
Liquid Rad-Waste System 1.1 Provide design and operating information for each of the process streams indicated on Figure 9.2.1 for the various pieces of waste handling and treatasat equipment. This information should iaclude but not necessarily be limited to:
a.
The volume in gallons of the following tanks:
(1) collection tanh (2) sample or monitoring takka (3) condensate storage tanks (4) distillate tanks b.
For each of the major source of radioactive material include:
(1) Average daily volumes, the number of batches per day, the volume per batch, and the expected flow rate.
(2) Normal and maxi - activity in uCi/ day.
(3) Normal and maximum activity concentration in uC1/cc.
1.2 Provide information as to the type, the rated throughput and the operating throughput of the evaporator. Provide also the expected decontamination factors for the various radieumelides contained in the liquid weste processed by the evaporator.
The rationale for selecting the particular malt and supporting data to show that the espected decontamination factors saa be achieved should also be included.
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2-1.3 Provide information as to the rated throughput, the operating throughput and the frequency of regenerating the domineralisers. Include the expected decontamination factors for the various radionuclides contained in the liquid waste processed through the domineralisers.
Provide information as to the typo of resin to be used and the total resia weights.
1.4 Cite appropriate experience and literature reference to support the decontamination factors assigned to the filters, domineralisers and the evaporat c.
1.3 Paragraphs 9.2.4.1 and 9.2.4.2 indicate that, on occasion, water meeting design limits may be discharged to accouano-date plant water inventories but fail to indicate the point of discharge. Figure 9.2.1 should also show the point of discharge.
2.
Solid Wastes 2.1 Describe in more detail the dowatering procedure and the method of fixation for immobilising the slurry discussed in paragraph 9.3.4.1.
It is not clear why it is necessary to store the drums three to six months before they are transported off-site for burial. Define high level and low level radioactive waste and the procedures used to sort the waste into these categories.
2.2 Paragraph 9.3.4.2 indicates that ventilation will be supplied to the hydraulic press-bailing machine to maintain control of contaminanated particles but fails to indicate whether the exhaust air is filtered and the point of discharge.
This information should be provided.
2.3 Provide projected daily aad or monthly and annual estimates of solid waste generated.
3.
Gaseous Wastes 3.1 Provide the appropriate values assigned to the circles and hazagons shown on Figure 9.4.1 for the various pieteW of gaseous waste handling and treatment equipment. This infor-nation should include but est necessarily be limited to The volume, in cubic feet per minute, of the a.
variose exhaust systems.
b.
Normel activity conaestrations, sci /cc.
c.
Hawimm activity concentrations, uCi/cc.
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. 3.2 Section 7.11.3.2 indicates that the of f-gas vent stream will be monitored by renoving a gas semple through an isokinetic prole located _ high enough in the vent stream to assure repre-sentative sarpling. Provide in more detail the essential
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features of the stack naupling probe and auxiliary equipment.
Provide the following:
a.
stack design volune and velocity b.
stack diameter c.
probe size d.
location of probe to assure representative sampling description of flow measurinF and recording equipment e.
f.
size of sample line and location.
Figure 9.2-1 shows a n' mber of tanks vented but fails to 3.3 u
indisate whether the off-has is treated and the point of dis-charge. This information should be provided.
3.4 Provide information as to the amount of charcoal in each of the proposed 16 charcoal adsorbers, the expected flow rates, and tho projected delay times for noble gases. Paragraph 9.4 indicates that the performance of the off-gas system should be improved by operating essentially the same equipment at a reduced tenperature (O'F versus 77'F).
Provide cata to show what the reduction in off-gas activity will be as a result of the lower operating tenpcrature.
Figure 9.4.1 shows a by pass around the charcoal adsorbers.
De er1Le the administrative controls and design features v
which will be employed to prevent discharging gaseous vaste without treatment.
3.5 Appendix C.O. which contains the design requirements for the off-gas equipment was not included.
3.6 Paragraph 9.4.7 indicates that HEPA filters will be periodically tested by laboratory analyses of inlet and outlet millipore filter samples. At best this is a qualitative test which lacks the sensitivity to detect and locate pin hole leaks in the filter media or by passing of air around the gasket and filter assently. Justify not using an in place D0P test which has a detection limit of 0.01% penetration. Discuss the testing program to assure that HEPA filters will meet the required efficiency of 99.97% prior to installation.
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4-4.0 Auxiliary Systems 4.1 Describe in more detail the fiiter-demineralisers used in the fuel pool cooling and cleanup system. As indicated in paragraph 10.5.4 the fuel pool water is normally re-circulatad except when draining the reactor well. Indicate the total capacity of the system, how frequengly the well will be drained and to where the water will be discharged.
4.2 Paragraph 10.9.7 indicates that the resoval of gaseous particulate contamination from the building ventilation system involves the use of high efficiency filters and activated carbon. The latter clean-up system is not shown on any of the schematics enclosed with the PSAR.
Provide a system schematic and indicate the design bases and operating parameters.
John T. Collins Radiological Safety Branch Division of Reactor Licensing cc: H.R.Denton R.Zavadoski R. P. Grill S. Miner DISTRIBUTION DRL Rdg.
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