ML19206A860
| ML19206A860 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/22/1972 |
| From: | John Miller Metropolitan Edison Co |
| To: | Muller D US Atomic Energy Commission (AEC) |
| References | |
| NUDOCS 7904210549 | |
| Download: ML19206A860 (9) | |
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METROPOLITAN EDISON COMPANY
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50-289 50-320 Septe=ber 22, 1972 o Go a
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Mr. Daniel R. Muller S
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D Assistant Director for Environ = ental Projects United States Atomic Energy Co==ission N
g Washington, D. C.
20545 Dear Mr. Muller Enclosed please find forty (40) copies of responses to coc=ents made by Federal and State Agencies in connection with the Co==ission's Draft I= pact Statement for Three Mile Island Nuclear Station Units 1 and 2.
This submittal includes only a partial response to these coc=ents.
The applicant will submit additional information with regard to these co==ents by Septe=1.er 29,1972.
Very truly yours,
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G. Miller Vice President
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e THREE MILE ISLAND NUCLEAR STATION, CIITS 1 A'ID 2 Application For Class 104b Utilization Facility Operating License DOCKET NOS. 50-289 AND 50-320 Applicant herewith subt: tits 40 copies of responses to cot::=en.:s made by Federal and State Agencies in connection with the Cot:: mission's Draf t I= pact Statement for Three Mile Islaad Nuclear Station Units 1 and 2.
METROPOLITAN EDISON COMPANY ATTEST:
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Sworn to and subscribed before =e this ay of --' -m 1972.
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n PISPO::SE TO EPA QUESTIO::S ON T'!I C; VIRO::ME::TAL REFORT, AEC DRA?I DTACT STATEME::T Radioactive Uaste Manc;enent Comnent, Item #1 The intended procedure for handling radioactive liquids from sluicing and re-generation operations is ccasidered "ts low as practical" in that it is the in-tention of the Metropolitan Edison Ccepany to process as much as these liquids, when radioactive, as can be handled by Units 1 siscellaneous radwaste evaporator.
These wastes will be discharged only if they are non-radioactive or the quantity exceeds the capacity of the evapcrator-demineralizer ntocessing system.
Co==ent, Iten #2 Space was provided in Unit 1 to add a deep bed demineralizer cendensate polish-ing system. The addition is dependent upon whether the existing Powdex filter /
denineralizer can effectively function with condenser tube leakage.
In the this system is added, the regenerate solution, when radioactive, will be event treated by miecellaneous radwaste system to the extent practical.
Co==ent, Item #3 In general, liquid wtste from the turbine building drains are not expected to con-tain.significant radioactive contamination. The possibility of contamination does exist in the event of plant coeration with both defective fuel and a primary to secondary system lerk.
The quantity of liquids entering the turbine building drains had previously been esti=ated(l) to be 7200 gal / day for both Units 1 and 2.
Assuming 0.l' percent defective fuel and 10 gpd primary to secondary leak, a conservative estimate of the activity content of this waste is approxicately.001 uc/cc for nixed isotopes.
These wastes will be discharged without treatment to the river via the efflu:nt (1) Source Term Input (Oak Ridge Questions)
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, from the tower blowdowr. and nuclear cad secondary service systems. Under these conditions,'" the average annual concentration in the discharge, prior to dilution in the Susquehanna River, will be 4.5 x 10-10 uc/ce.
Effluent Monitorin2 Comment, Item #5 The normal and potential paths for release of radioactive caterials during nor:al reactor operations will be monitored. The release of liquids from the secondary coolant system (turbine building drains, powdex filter, demineralizer sluice water and deep bed demineralizer regenerate solutions) will be discharged via the flow and radiation monitor box.
In the event of plant operation with defective fuel and a primary to secondary sys ten leakage, these vastes will be sampled and analyzed on a regularly scheduled basis. It is the intention of the Metropolitan Edison Company to co= ply with the recommendations of Safety Guide 23 regarding effluent monitoring to the exte,nt practicable.
A tabulation of the quantities of radionuclies which could be released undetected due ta instru=ent sensitivity limitations from the various release points in the plant are as follows:
Undetected Quantity (uc)
Release Point o r Release Rate (uc/sec) 1.
Condenser Vacuum Pump Exhaust via Monitor Rm-A5 Noble Gasses (Kr-85) 1.4 x 10-2 uc/sec Iodine (I-131) 1.4 x 10-2 uc/sec Particulates (Cs-13 7) 1.4 x 10-2 ue/sec Note: Any one or combination of the above that results in a release rate of 1 4 x 10-2 uc/sec will be detected. Anything less than this activity flow rate could go undetected.
If the release consists of iodire and/or particulates, this would be detected at the first scheduled saepling interval af ter the release occurs.
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Release Point or Release Rate (uc /=ec) 2.
Auxiliary and Fuel Handling 31dg.
Exhaust-via Monitor Rm-A8 Noble Cases (Kr-85) 225 uc/sec Iodines (I-131) 160 uc*
Particulates (Cs-137) 800 uc*
- Between sa=pling intervals 3.
Reactor Building Purge Exhaust-via Monitor Rm-A9 Noble Gases (Kr-85) 50 uc/see Iodines (I-131) 68 uc*
Particulates (Cs-137) 340 uc*
- Between sampling intervals 4.
Plant Liquid Ef fluent Discharge via Monitor Rm-L7 Mixed Isotopes 4.5 ue/sec This release, rate corresponds to a concentration of 2 x 10-6 uc/cc in the plant discharge to the river. Anything less than this activity concentration vill be released undetected.
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. Conment, Ite= #6 An analysis of flood discharge-frequency relationship was made using data gathered by the U.S. Geological Survey on past floods dating back to 1786. Until recently, the flood of record was that of March 19, 1936, which, according to the U.S. Geological Survey, was the highest known flood to have occurred since 1734 and probably the highest since 1740. The 1936 flood at Harrisburg was gaged at 740,000 cfs and resulted frc a large scale snou relt over the entire area of Pennsylvania.
On June 24, 1972, a record
- flood of approximately 1,000,000 cfs occurred at Harrisburg as the result of tropical storn "Agnes" moving slowly up the eastern seaboard and depositing an average rainfall of 8 inches on the Susquehanna River basin. Maximum rainfall depth in the basin totaled 17.7 inches during a period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. During chis period, about 12 inches was incident on the site at Three Mile Island.
s Preliminary estimates of :he 1972 flood at Harrisburg place the frequency of occurrence at approximately once in 500 years, as indicated by the curve shown in Figure 2.5-12.
The design flood established for the site is 1,100,000 cfs, which was based upon the provisional probable maximum flood established by the Corps of Engineers prior to 1969. The hydraulic design of the plant inundation protection facilities is based upon the design flood to provide adequate protection with an ample margin of f ree-board. The generating station and its facilities will not have any significant effect en local conditions during the design flood.
The conservatism used in designing the facilities to protect the plant from the design flood was evidenced during tropical scorn "Agnes", which in effect produced a flood approaching the design flood in magnitude. The maximun water surfcce in the river at the site during the 1972 flood was at elevation 300.5.
The curves c e, a C. tk C.f.
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. shcun on Figure 2.5-13 of the Envircnnental neport indicate that fer a flow of 1,000,000 cfs the water surface at the site (Goldsboro) would be at elevation 1
302. Thus a 3.5 foot freeboard nas been provided in design against overtopping for an Agnes flood, since the Icx 2s dike elevation south of the site is 304 Had Three Mile Island :iuclear Station been completed and operable during the 1972 flood, it would not have experienced any adverse effects, since the dike syste: would have afforded adequate flood protection.
Metropolitan Edison Cc=pany and Pennsylvania Pcwer and Light Company are planning a joint pumped storage project on Stony Creek, approximately 13 miles northeast of Harrisburg. The project etrsists of a lower das and reservoir on Stony Creek and an upper reservoir between Stony and Sharp Mountains, providing a head of 975 f t.
for peak-power generation of 1,100 MJ.
The project will have no known adverse effect on Three 1 Ele Island, but will improve conditions on the Susquehanna River by af fording some degree of flood protection and augmentation of low flows.
The Stony Creek Pumped Storage Project is in the preliminary design state.
Fin al design is expected to begin in about two years, based upon a presently planned in-service date of 1983-84. Detailed design data is therefore not available; however, it is planned to provide sufficient spillway capacity to pass its local probable eaxinu: flood, based upon the applicable basin PMF, Consideration will also be given in the design to enable the dass to withstand seismic effects, but neither the design criteria or caterial properties has been established.
Stony Creek dan will be approximately 100 feet in maximum height and will impound about 24,000 acre feet of water depending upon the final pool elevation. The dam will be an earth embankment constructed with local materials and have a concrete spillway. Assuming a seis=ically-induced dan failure at times of normal strean flow, and the consequent loss of the reservoir volute during a conservative one-hour period, the resulting avercge downstrean ficw would be in the order of 300.000 a.a..e n D.<t ce
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. The 24-r.11e flow route to the plant site vould serve to attenuate both the cfs.
peak flow and flood wave, especially in the broad 4,000 ft-wide Susquehanna River.
A flow increase of 300,000 cfs at the plant site would raise the river level about 7 feet above the normal elevation of 280. Such an occurrence will not have any a minimum elevation of 304 and adverse effect on the plant since the dikes are at provide a 24 foot protection for such an event.
"The filters pas 2,000 gph Page 3.7-2 of the Environmental Report states that, The ficw from each of the clear fi'.:ered water to the cooling water discharge."
This water is essentially the same or better two filters vill be 66 gpm maximum.
It will be taken frcm the river except suspended matter is removed.
than that The effect on the river will be blended with 36,000 gpm of plant cooling water.
is present insignificant unless a high concentration of any particular centaminant in the filtrate. ;This is not the case.
Radioactivity to the sludge treatment building from spent Powdex waste solution will If there is a primary to secondary steam generator tube leak, the be controlled.
contaminated Powdex waste will not be transferred to the sludge treatment building.
It will be pumped to the radwaste system for treatment.
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RESPONSE TO PARACKAPH 4 0F THE JULY 26th LETTER 07 REAR /CMIRAL U. M. DE"KEFT TO ?'E DA'JIEL R. M'LLER s
It is hera pointed out as a =atter of reccrd and clarification that the piumes which will emanate from the cooling towers at Three Mile Island are not smoke, in the most cc=monly accepted usage of that word, which has to do with some sort of co=bustion or other particle producing process. The effluent from the cooling towers consists of water, in the for= of very small droplets and as a vapor, cixed with atmospheric air which merely passes through the tower.
With regard to the potential effect of the estimated 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> per year, this =ay be more accurately described as a persistent but elevated plume rather than fogging which infers a ground level effect.
Experience at other locations with operating towers comparable to those at Three Mile Island indicates there is a very minimal effect on even the lightest air craft in penetrating the plur'e, comparable to penetration of a cumulus cloud. The persistent plume will be adequately elevated (of the order of 700 to 1,000 feet above grade) t o p e r=1t VFR landing and because of the relative position of the towers with respect to the air-port approaches it is not conceivable that the plumes would align their longest dimension with the approaches. Due to the random direction of wind it may some-times be necessary for approaching aircraft to penetrate the plu=es, but this will be along their short dimensica for a very brief interval, and they will emerge frac the plume well before any lower limit of VFR restrictions. This is the potential effect whica is estimated to be 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> per year.
We concur with the opinion of Rear Admiral Denkert that this impact is minical and that an operating license should be issued.
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