ML19220C190
| ML19220C190 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/02/1974 |
| From: | Tedesco R US Atomic Energy Commission (AEC) |
| To: | Kniel K US Atomic Energy Commission (AEC) |
| References | |
| NUDOCS 7904300039 | |
| Download: ML19220C190 (3) | |
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- t. Iniel Light Water Ecectors 3 ranch 2-2,L RCU:SD OC QUESTIONS FOR TTCZ ICLE IS747m
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Plant Nare:
ftcensing Stage-Three Mila Islaad, Unic 2 Docket Number:
Responsible Branch:
L7?. 2-2 Project Imader:
- 3. Washburn Requested Coepiction Date:
Description of Saspouse:
August 2. 1974 AAdf tional Infor :ation Reviev Status: Under F d.ev 7e have reviewed the FSA2 for Three Mila Isl determined that the enclosed additio:ial inforn tiand, Unit 2 and have to complete our revis:i.
on is necascary a
'Je need responses by Octob er 13, 1974, to meet our schedule.
Ecbert Tedesco, Assistant Director for Conraimumt Safety Directorata of T.fernsing Enclosure.
As stated D_ISTIIBUTION -
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01-1 ROUND ONE QUESTIONS FOR THREE MILE ISLAND, UNIT 2 Docket No. 50-320 01.0 EFFLUENT TREATME'ir 01.1 (11.2.3)
Describe the provisions cade to assure representative sampling of processed liquid radwaste prior to disposal in confor=ance with Regulatory Guide 1.21.
01.2 (11.2.2)
The Miscellaneous Waste Chain wastes fro: Three Mile Island Unit 2 are transferred to the Three Mile Island Unit 1 Miscellaneous Waste Chain for treat =ent by evaporation and de=ineralication.
Since only one 12.5 gp evaporator has been provided for the wast'es fro = both plants, discuss your contingency plans for the treatment of this waste strea=
in the event of a prolonged outage of the evaporator unit and/or for periods of abnor ally high radwaste input flows.
01.3 (11.2)
Provide a. table listing tanks outside reactor containment which ccatain potentially radioactive caterials.
The table should include tanks located both inside and outside of plant buildings.
For each tank indicate the provisions incorporated to conitor tank levels, to annunciate potential overflow conditions, and to collect and process liquids in the event of an overflow.
Acceptable previsions include dikes around tanks, retention basins, and elevated thresholds to contain liquids in bays containing the tanks.
01.4 (11.3)
For HE?A filter and charcoal adsorber installations in building ventilation syste=s, provide the following infor=ation:
(1) Acceptable design pr:ctice in the use of EEPA filters ifmits individual filter systers to a capacity of 30,000 cf: (li=it 3 EEPA filters high and 10 EEPA filters wide).
Justify your operating the Auxiliary 3uilding EE?A filter syste=s (2 banks of' 30 HEPA filters) at a design flowirate of 41,945 cf: per syste=.
D'escribe the layout of the filters for ecch syste=.
(2) List 'he assumed residence ti=e for charcoal adsorbers and the efficiency of iodine retention. Justify your assu=ed efficiency for iodine retention by test data (te=perature, pressure, humidity, e:cpected iodine concentrat ns, and flow rate). Describe the effects of aging and poisoning by toisture and airborne conta=inants and support your assumptions by test data.
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01-2 31.5 (11.3)
Describe the Waste Gas Filter Syste= identified as WDG-F-l'on Figure 11.3-1.
Discuss your reasons for not providing HEPA filters af ter charcoal adsorbers in the Waste Gas Filter Syste=.
01.6
( 11. 3. 2.1)
In describing your provisions to eliminate the possibility of a hydrogen explosion, you state that the Radwaste Gas Syste= is periodically monitored at several points for oxygen and hydrogen. Show the locations of these monitors on the P&ID's, and justify why continuous =enitoring is not needed.
01.7 (11.5.6)
Specify the di=ensions and location of the Additional Storage Area provided for packaged solid radwaste on the 305' elevation of the Fuel Handling Building. Provide the number of dru=s and types of wastes to be stored in this location and the provisions for =enitoring and surveillance of stored wastes. Describe the storage facilities provided for the decay of short-lived radionuclides prior to shipment and give the anticipated storage ti=e prior to shipment and the bases for'the value selected.
01.8 (11.5)
Describe methods that will be used to ensure the absence of free water in solid waste dru=s.
01.9 (15.24)
Previde an analysis indicating the radionuclide concentrations which could occur in both 1) the nearest potable water supply, and 2) the nearest surface water. in an unrestricted area as a result of leakage based on single failures of components located outside reactor containment containing radioactive liquids.
Assume 1% of the operating fission product inventory is released to the primary coolant, failed tanks release 80% of their design capacity, and all liquids fro: failed components enter the groundwater; i.e., do not assume liquids are retainec by building foundations. Credit for radionuclide re= oval by the plant process syste=s, consistent with the decontanination factors in WASH-1258 should be assumed. List all para =eters and provide justification for the values assu=ed in your calculations, including liquid dispersion and transit ti=e based on distance, the hydraulic gradient, permeability and effective porosity of the soil, and the assu=ed deconta=inatien due to ion exchange by the soil.
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