ML19312C713
| ML19312C713 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/03/1969 |
| From: | Howe P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912190921 | |
| Download: ML19312C713 (8) | |
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OCT 3 1m R. 5. Boyd, Assistant Director for teacter Projects, DRL THRU:
S. Levine, Assistant Director for Reactor Technology, DRL QJESTION LIST POR DUEI POWER COMPANY - DOCKET N06[ 50-269A70 4 287
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Attached are our questions for Duke Power Campany - Oeesee Reactor. Additional questions any be raised as review progresses.
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P. W. Newe, Orief Environmental 4 Radiatica RT:742A Safety Technology 3 ranch E4RSTE:DRL RN Division of Reactor Licensing Emelosure:
Dessee Questians cc w/saclosure:
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DUKE POWER COMPANY l
OCONEE QUr1TIONS DOCKET NOS. 50-269, 270, 287 Site and Environment 1.
What is the total permanent and transient population in the LPZ?
What are corresponding numbers for the distance at which a dose of 300 rem will be received during the fir t 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the MiA?
i 2.
In order to evaluate the effect of routine liquid waste discharge, how many stream miles is it to the Clemson and Anderson municipal water intakes? What is the daily consumption at these locations?
3.
Justify the lack of any onsite environmental monitoring in the
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e predominant downwind directions (south and east) or at the onsite residence. We prefer that a monitoring station should be established for surface water and sediment in Hartwell reservoir somewhere near the one mile exclusion boundary, since this is near the liquid d
discharge point.
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We interpret the last sentence on page 2-12 to mean you feel free to l
cease the environmental monitoring program at your own discretion.
Please formulate a more definite description of proposed permissible changes in the extent of monitoring as related to releases of activity l
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C-a from the facility. We have no objection to permitting variations in
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the amount of monitoring performed, but will require a definite plan for doing so.
5.
The accident doses presented are based on the same valley drainage atmospheric diffusion model used in the PSAR. However, you are expected to provide onsite data to support this model, since it is somewhat less conservative than that normally applied. To date, this has not b en done.
In fact, the present onsite data seems to refute the model strongly. We must, therefore, request that additional onsite data be taken and submitted to support the model you have used.
Otherwise, it will be necessary to use a much more conservative model, which may produce unacceptable doses.
Engineered Safeguards i
1.
Since the penetration room must be regarded as an engineered safeguard, considerable additional information is required.
Describe in detail the boundaries of the sealed area bearing this designation, identify all penetrations to other parts of the auxiliary building, describe the type seals used on these penetrations, c
particularly for personnel doors, and indicate whether air locks are provided.
Indicate the general composition of the walls, floors, and ceilings, indicate under what circumstances integrity of this space will not be required, including time periods.
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Thepenetrationroomventijationsy,stpmhasbeenidentifiedasan engineered safeguard.
In order to evaluate its operation, we will need the following: What is the flow vs. head characteristic of the fan; how much pressure drop at 2000 cfm flow is expected for i
the following: Clean filters, dirty filters, total system ducting, building negative pressure. What provision is there for regulating building pressure and what are the reliability factors involved? What are the sizes and design flows of the suction lines from the hatch seals outside the penetration room area? How do these flows compare with the maximum permissible leakage rates?
What is the design negative pressure to be maintained in the penetration room?
If this is less negative than 0.5" wg, provide the area in square feet of this room which is exposed to the outside temperature, a description of all joints in this area which could leak, and an f
analysis of the effects of high winds on this leakage. What is the design leak rate (cfm) of the rcom at maximum pressure difference?
Is this system system and that for the auxiliary building completely independent?
o 3.
Efficiency tests will be required on the penetration room and gaseous waste system filters for particulates. and iodine. Are there connections provided for inplace testing? Describe the general test method, including tise of injecting test material.
What test materials will be utili:ed? What are the minimum efficiencies which must be met in l
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these tests? How will the type of charcoal actually contained in the filters be verified? For the penetration room filters only, also provide the following: Will the test materials have any future effect on filter performance during accident conditions? What
,.ovisions are there for moisture control in the filters between tests and during the MHA? What is the size of the crossover line between the two filter systems? Are there provisions for automatic usedof this line to cool filters loaded with fission products after a fan fiils?
What is the magnitude of this cooling flow, the predicted maximum filter heat load and temperature under these conditions? What is the mass of charcoal bed, its dimensions, depth for filtering, and iodine contact time?
4.
What radiation source was used for determining doses to operators in the penetration room and control room during the MHA7 What are the p
expected doses?
Waste Disposal Systems 1.
Since filters are available, please justify the intent to bypass them during building purge operations if the concentrations are higher than the MPC for unrestricted areas, in view of the " reasonable effort" requirement of Part 20.
Likewise, justify not utilizing the ho1 dup tanks provided when disposing of low level liquid or gaseous waste which is above MPC in the discharge line.
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2.
Referring to page 11-14, what is the maximum operating pressure of
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waste gas tanks? Since the design pressure of the liquid waste tanks is only ten feet of hydro head, what problems will occur if their vents are connected to the pressurized gas decay tanks by valve malfunction:
If this is significant, does the control system meet the redundancy and reliability requirements of the IEEE7 3.
Referring to page 11-16, monitor RIA-36 on the reactor coolant line has an upper range of 50 uc/ml. Justify useage of this low range when the concentration in the coolant with 1% failed fuel is expected to exceed 300 uc/mi.
The information cri ranges of most of the monitoring instruments in Table 11-5 is difficult to interpret.
Please clarify by stating the ratio of the maximum range to the level expected for operation with 1% failed fuel.
4.
List the tanks considered in determining the total system capacity
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de=cribed on page 11-22, which appears to be approximately 65,000 cubic feet.
Indicate the number of tanks per unit, and which tanks are shared by all three units. What types of restrictions are there on passing borated water, decontaminated coolant, and liquid wastes y
from one reactor to the other? Does this flexibility tend to increase the probability and consequences of cperator errors?
What operational and administrative distinctions are there between waste disposal system tanks, and other facility tcnks?
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Provide more information on the use of the waste gas exhauster 4
shownCLn figure 11-3.
Since it is apparently intended for release of low level gaseous waste, prudent design would include valves for isolating it from the liquid system vent hesder and other high level sources, but this is not indicatedcin the figure.
Explain the discrepancy in the number of waste gas tanks:
Figure 11-3 shows two tanks, while Table 11-4 Lists four tanks.
Do they all have the same volume and pressure rating?
6.
Justify the apparent intent to dump liquid and gaseous wastes over short time periods, when system capacity apparently does not require this.
(It reduces the dilution possible in the environment).
7.
Are there any conditions under which reactor operations would be restciced or prohibited because of lack of residual capacity in the liquid tank ^ age? Indicate the minimum available volume which can be tolerated in each type of tank while continuing reactor operations.
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Will operation of the three units be controlled or restricted to i
avoid excessive liquid disposal in a short time (such as two startups)?
l Accident Analyses 1.
Where does the excess coolant due to accidental rapid moderator dilution go? How long could the flow be as high as 500 gpa? What is the total volume of water dumped, maximum total activity content, and initial disposition outside the primary system 7 Is this tankage always available?
2.
Justify the absence of filters on the iodine release from a refueling accident.
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Regarding the use of the reactor building purge system described on f-page 14-64, is use of this system pYmissible while the reactor operating or at pressure? What is the maximum time required to purge the building of the highest expected levels of activity? What is the normal flow rate through the purge system, and what is the rate if the containment pressure is 59 psig as described?
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