ML19308D939
| ML19308D939 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/08/1972 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| 1910, NUDOCS 8003200688 | |
| Download: ML19308D939 (24) | |
Text
_ _ _ - _ _ _ _ - _ _ _ _ _ - _ _ _
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DaTE RecovEo No.:
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Ltr re our 3-24-72 ltr, trans the Benaroya 4-10 "2 following:
W/4 cys for ACTICH QISTRIBUTION ges File gaanrtsfelder Basic Dnt, For Bource Thra Calculation i.EC PDB for Crystal River Unit 3 compliance (2)
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\\sf April 8, 1972 Mr. R. C. DeYoung Assistant Director for tl D
Pressurized Water Reactors
,Pf Division of Reactor Licensing Y
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Dear Mr. DeYoung:
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In Re:
Florida Power Corporation
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Crystal River Unit 3 lj N.._O +
d Nuclear Generating Plant Docket No.
50-302 Enclosed are forty-five copies of the Florida Power Corporation response to data requested in your letter of March 24, 1972.
As we indicated in our letter of March 31, 1972, we are sending separate l
copies to Mr. Tom Row /of ORNL for review prior to the April 13-14 meeting.
Florida Power Corporation representatives will attend this meeting for further discussion.
cy3 Very truly yours, 4
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. 91 APR10 J.E.Rodsers'lLLa i
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1910
PRESSURIZED WATER REACTORS CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PIAvr BASIC DATA FOR SOURCE TERM CALCULATION Question #1 - Operating. Power (MWt) at wktich impact is to be analyzed.
Answer:
The basis for the analysis in the Environmental Report is a power level of 2772 MWt.
Que= tion #2 - Weight of uraniun loaded (first loading and equilibrium cycle)
Answer:
The first load of fuel will consist of 93.1 metric tons of UO2 (Table 8-2 FSAR).
The rate of uranium loaded in the equilibrium cycles will be 31.0 metric tons at each refueling. The initial fuel cycle time is 430 full power days and the equilibrium cycle is 310 full power days.
Question #3 - Isotopic ratio in fresh fuel (first loading and equilibrium cycle) e a
O e
w---'=
y y
74w g
Answer:
The initial fuel loading will contain an average U-235 content of 2.44 weight percent (Table 3-2 FSAR). The fresh fuel in the equilibrium cycles will contain an average U-235 content of 2.86 weight percent.
Question #4 - Design basis percentage of leaking fuel Answer:
This value is given in FG. 11-1 of the FSAR and Table VII-2 of tne Environmental Repert. The nu=crical values are es follows:
Environmental Report 0.1%
Safety Analysis Reports 1.0%
l Question #5 - Escape rate coefficient used (or reference)
Answer:
The numerical values are as follows:
i Element Escape Rate Coefficient Kr, Xe 6.5 x 10-8 Br, I, Ce, Rb 1.3 x 10-8 Te, Se, Pd, Ag, Sb 1.0 x 10-9 f'
Cd, In, Sn Mo, Nb, Tc, Ru, Rh 2.0 x 10-9 Sr, Ba 1.0 x 10-11 V, La, Ce, Pr, Zr, Nd 1.6 x 10-12 Sm, Eu Question #6 - Plant factor Answer:
Based on an eighteen year projection study, the plant factor, defined as megawatt hours generated per year averages out to be.80.
This was capacity (mw) x 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year, used for analysis in the environmental report.
Question #7 - Number of steam generators?
Answer:
The number of steam generators is two.
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Question #8 - Type of steam generators?
Answer:
Both steam generators are vertical - once through type, with integral superheater.
Question #9 - Mass of primary coolant in system total (lbs.) Mass of pri-mary coolant in reactor (lbs.)
Answer:
Tha normal volune of hot reactor coolant, average temperature of 580*F, in the total reactor coolant system is 11,478 ft3 (Table 1-1 FSAR) and the mass is 514,000 lbs. The volume of hot reactor coolant in the reactor vessel is 4098 ft3 (Table 4-3 FSAR) and the mass is 181,000 lbs.
Question #10 - Primary coolant flow rate (lbs. per hr).
Answer:
i The reactor coolant flow for Crystal River Unit No. 3 is 131.32 x 106 lbs/hr (Table 4-3 FSAR).
Question #11 - Mass of steam and mass of liquid in each generator (1bs).
Answer:
The amount of reactor coolant in each of the steam generators is 2030 ft3 (Table 4-4 FSAR) and the mass of hot reactor coolant is 91,000 lbs.
Themassofsteamandwateronthesecondarysideoheachsteamgeneratoris 4600 and 43,000 lbs respectively at rated full power.
Questi'on #12 - Total mass of secondary coolant (1b)?
Answer:
The mass of secondary coolant circulating in the secondary loop is approximately 1.8 x 106 lbs. This can be broken down as follot s:
Feedwater heaters 254,900 lbs Piping 20,000 lbs Steam generators secondary side (2) 86,000 lbs (steam) 4,600 lbs Deaerator 600,000 lbs l
Condenser Hotwell 830,000 lbs i
r TOTAL 1,795,400 lbs In addition, there are two condensate stoarge tanks with a total capacity of 200,000 gal. (1.67 x 106 lbs.)
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Question #13 - Turbine operating conditions (temperature, pressure, flow rate)
Answer:
At full rated power, the operating conditions are:
a.
Temperature, 570*F (35'F superheat) b.
Pressure 910 psig c.
Steam flow 11.2 x 106 lb/hr.
Question #14 - Total flow rate in the condensate demineralizer (lbs per hr)
Answer:
The maximum total flow rate in the condensate demineralizers is 7.87 x 106 lbs/hr.
3 Question #15 - What is the containment volume (f t )7 Answer:
The reactor building internal free volume is 2.00 x 106 ft3 Question #16 - Expected leak rate of primary coolant to the containment building.
O Answer:
This value is given in Table VII-6 of the Environmental Reporr as 100 gallons per day or about 24 lbs. per hr.
1 Question #17 - a.
How gften is the containment purged?
b.
Is it filtered prior to release?
c.
Are iodine absorbers provided?
d.
What decontamination factor is expected?
Answer:
It is planned to purge the reactor building periodically for personnel access for maintenance and inspection. Tentative schedule is once per month.
The reactor building purge exhaust is filtered through roughing, HEPA and charcoal filters prior to release. Radioactive iodine will be absorbed by the charcoal filters.
1 The charcoal filter efficiency assumed in the environmental report is 97 percent (decontamination factor 1/3).
These filters are rated and tested at 99.93 percent efficiency for removal of elemental iodine.
Question #18 - Is there continuous air clean up for iodine in containment?
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Answer:
There is no systam provided for continuous air cleanup of iodine in reactor building or Crystal River Plant Unit #3.
Question #19 - Give the total expected continuous letdown rate (1b/hr).
a.
What fraction is returned through the demineralizer to the primary system? What is the expected demineralizer efficiency for removal of principle isotopes?
b.
What fraction of this goes to the boron control systee? How is this treated: demineralization, evaporation, filtration?
c.
Is there a separate cation demineralizer to control Li and Cs?
Answer:
The nonnal expected letdown rate is 45 gpm (one reactor coolant volume per day or about 21,500 lbs per hour).
All of the letdown flow is passed through a purificaiton demineralizer.
a.
The expected purification demineralizer decontamination factor is 100 for all nuclides except Cs, I, Nb, Kr, Xe, and Tritium which are 1.
b.
The annual. letdown to the liquid waste disposal system'is 15,000 ft3, Two methods of boron control are utilized. They are:
(1) bleed and~ feed when the boron concentration in'the reacto: coolant is above about-270 ppm and, (2) deborating demineralize when the boron concentration in the reactor coolant letdown from the primary system passes through a makeup and purifi-cation demineralizer.
In the case of bleed and feed, the reactor coolant letdown is collected in the reactor coolant bleed tank after it has passed through the purification demincralizer.
The bleed tanks are connected to the low pressure waste gas header so that any gases evolved.from this letdown are collected and stored in the waste gas decay tanks. The liquid collected in the reactor coolant bleed tank may be treated by filtration and demineralization in cation and mixed bed demineralizers and evaporation
$n tha. liquid radwaste system. Various combinations are possible but the minimum treatment is evaporation followed by demineralization of the evaporator distillate.
1 I
In the case of deboration in a deborating demineralizer, the reactor coolant passes through the purification demineralizer before entering the deborating demineralizer and is ultimately all returned to the primary system via the makeup tank and makeup pumps.
c.
There is no specific cation demineralizer in the makeup and purification system for the removal of Li and Cs.
However, a fresh charge of resin can be maintained in one of the two purification demineralizers. When specified control of Li and/or Cs is required, the letdown is re-routed through the fresh resin bed.
Reactor coolant letdown in the reactor coolant bleed tanks may be processed through the cation resins of the liquid radwaste system for removal.of Li,and/or Cs as required.
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Question #20 - a.
What traction of the noble gases and iodines are stripper.
from that portion of the letdown stream which is demineralited to the primary return system?
b.
How are these gases col-lected?
c.
What decay do they receiv'. prior to release?
Answer:
It h:= been ::su=cd in crri.-ing ct the equilibrium reactor coolant a.
activities that there will be no stripping of the noble gases and iodines from the letdown stream of the primary coolant.
b.
The noble gases and iodines that are contained in the vapor space of the makeup and purification tank are vented once per year to the low pressure vent header system and collected in the waste gas decay tanks.
These gases will be stored approximately 90 days prior to release to c.
environs.
l Question #21 - a.
What fraction of the noble gases and iodines are stripped from that portion of the letdown stream which is sent to the boron control systen?
b.
How are these gases collected?
c.
What decay do they receive prior to release?
Answer:
8 One hundred percent of the noble gases and one percent of the iodines ~ are a.
stripped from R. C. letdown and vent to gaseous waste disposal system.
b.
These gases will be released into the low pressure vent header system and subsequently collected in the waste gas decay tanks.
These gases will be stored and decayed for approximately 90 days prior to c.
release.
Question #22 - Are releases from the decay tanks passed through a charcoal absorber? What decontamination factor is expected?
Answer:
All gases released from the waste gas decay tanks will be made through charcoal and HEPA filters in the Auxiliary Building Ventilation exhaust system. The de-contamination factor used in the environmental report is 20.
These filters are l
rated and tested at 99.93 percent efficiency elemental iodine removal. '
q Question #23 - a.
Ecw frequently is the system shut down and degassed?
b.
How many volumes of the primary coolant system are degassed in this way each year?
c.
What fraction of the gases present are removed?
d.
What fraction of other principal nuclides are removed, and by what means?
e.
What decay time is provided.
Answer:
The gystem will normally be shutdown and degassed once per year prior to a.
refueling.
b.
One primary coolant volume is degassed in this manner.
It is assumed that the majority, essentially 100 percent, of the volatile c.
gases present will be removed. Operating experience has indicated a certain frac; ion of the noble gases will remain in the primary coolant.
In comparison to the quantity removed, this fraction is extremely small.
d.
Other principle nuclides will be removed by the makeup and purification system during cooldown.
If one system volume is passed through in this manner a reduction of 100 is realized.
1 The gases of the system will be collected in the waste gas decay tanks and e.
decay for 90 day period prior to release to environs. )
.3 Question #24 - Are there any other methods of degassing (that is,- through
. pressurizer)? If so, describe.
Answer:
To remove fission product gases and other noncondensable gases from the pres-surizer steam space, two paths are used. ' In the first, 'the pressurizer 'is vented to the waste disposal system via the reactor coolant drain tank con-.
..nection to the pressurizer vent line. The preferred method for degassing the pressurizer is from the pressurizer vent line, thru the pressurizer steam space sample lines in the chemical addition and sampi.ng system where it returns to the makeup system upstream of the curificc* ion filters. By controlling the
= keup tank preccure, the remove, acc _rc diccharged to the uccte dispecal system until a reactor coolant gas sample indicates she desired conditions have been met.
Question #25 - If gas is removed through the pressurizer or by other means, how is it treated?
Answer:
Cases removed from the pressurizer are vented to the low pressure vent header system in the gas waste disposal system. These gases are collected in the gas decay tanks, and decayed for 90 days prior to release. These gases are treated as stated in the Answer to Ques
- fon #22.
Question #26 - What is the expected leak rate of primary. coolant to the secondary system (lb/hr)?
Answer:
i A primary to secondary leak is not normally expected during continuous' power operation. However, for the purpose of estimating radioactive releases via these modes a 10 gallon per day leak has been assumed in the Environmental
..Re por t. This is equivalent to approximately 2.5 lbs/hr.
Question #27 - What is the normal rate of steam generator blowdown? Where are the gases from the blowdown vent discharged? Are thare chcrecal abscrhers on the b1:wdown tank vent?
If sc, what decontamination factor is expectad?
Answert There is no steam generator Flowdown with the B&W system.
Question #28 - a.
What is the expected leak rate of steam to the thrbine building?
b.
What is the ventilation air flow throuc!1 the turbine building (CFM)?
c.
Where is it discharged?
- d. Is the air filtered or treated before discharge?
e.
If so, 4
p* ovide expected performance.
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Answer:
a.
The expected leakage rate of steam and condensate to the turbine building is estimsted to be 7 gpm steam and condensate.
(estimate 5 gpa steam, 2 gpm condensate) 1 b.
The ventilation air flow through the turbine building hall is 523,000 cfm.
c.
The air is discharged from the roof of the turbine building from a vent at Elev - 211'-0".
d.
This air is not filtered or treated prior to release.
Question #29 - a.
What is the flow rate of gaseous effluent from the main condenser ejector?
b.
What treatment is provided?
c.
Where is it released?
Anster:
a.
The flow rate of gaseous effluent from the main condenser ejector is designed for 15 SCFM; expected operationally is 7.5 SCFM.
Gas activity monitors are provided on the exhaust.
b.
No treatment is provided for this exhaust.
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c.
The fischarge is -from a vent on the top of the turbine building (elev. - ?.11'-0").
Question #30 - What is the origin of the. steam used in the gland seals (i.e.,
is it primary steam, condensate, or demineralized water from a i
separate source, etc.)? How is the effluent steam from the gland seals treated and disposed of?
Answer:
The steam used in the gland seals is main steam.
The gland seal steam is condensed in the gland steam condenser and returned to the system.
Question #31 - a.
What is the expected leak rate of primary coolant to the auxiliary :uilding?
b.
What is the ventilation air flow thru the auxiliary building (CFM)?
c.
Where is it discharged?
d.
Is the air filtered or otherwise traated before discharged?
e.
If so provide expected performance.
Answer:
For the purpose of the environmental report:
The expected leak rate of primary coolant to the auxiliary building was a.
assumed to be approximately 25' gallons / day..-
b.
The ventilation air flow through the auxiliary building is 156,680 CFM.
The ventilation air flow is discharged through the auxiliary building c.
sto k at clevation 276'-0".
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d.
The discharge is through roughing, HEPA, and charcoal filters, prior to release to atmosphere.
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,e.
The charcoal filters were assumed to have an iodine removal efficiency of 95% and the corresponding decontamination factor is 20. The ch'arcoal filcers are rated and tested at 99.93 percent efficiency for elemental fedine removal.
Question #32 - Provide average gallons / day and uc/cc for the following categories f
of liquid effluents.
a.
High-Level Liquids -
,, Avg / gal / day Activity-uc/cc Primary Coolant Letdown 250 Table VII-2, CR-3 Environ Report
" Clean or Low Conduc-tivity Liquids 250 e=10-5 Equipment Drains 185 Table VII-2, CR-3 Environ. Report 1.
The number and capacity of collector tanks for all wastes is presented in Table 11-5 for Crystal River Plant Unit 3, FSAR.
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2.
It is planned to recycle as much of this waste as practical.
Factors controlling decision are tritium buildup, pH, chloride and fluoride content.
In the environmental report, it is assumed that.85' percent of the prl 2ry coolant letdown is to be discharged after processing to control '.ritium concentration. Tritium concentration is to be maintained at less than 1.0 ue/cc at refueling.
3.
These wastes will be processed through:
Purification Domineralizer - DF - 100 for all nuclides except Cs, a.
Y, Mo, Xe, Kr and H-3 for which a DF - 1 is used.
b.
Cation Damineralizar - DF - 50 for all nuclides except Y, Ho, Xe, Kr and H-3 for which a DF of 1 is used.
c.
R.C. Evaporator / Condensate Demineralizer - DF - 300 for all nuclides except Kr, Xe and H-3.
4.
The average decay time for liquids removed from the primary system before discharge is 7 to 14 days.
5.
The expected volumes of solid wastes is given in Table 11-4 (III) of the FSAR.
Resins will be stored and shipped off-site in approved containers or shielded truck mounted cask.
Evaporator bottoms or concentrated boric a
3 acid will be reused when possible or solidified and drummed for off-site shipment when not.
An estimate of the number of curies generated per day is not available.
b.q " Dirty" wastes consisting of miscellaneous system leakage, laboratory wastes and resin sluice water are eetimated to be approximately 250 gal / day; estimated' activity content is 1.5 uc/cc mixed isotopes.
1.
See answer to a-1.
2.
It is planned to recycle as much of this waste as practical.
Factors controlling decision are tritium buildup, pil, chloride and flouride content. No discharge of this veste was assumed ir. the environmental report.
3.
These will be processed through:
a.
Cation Demineralizar - DF - same as item a-3b.
b.-
Miscellaneous Waste Evaporator / Condensate Demineralizer - DF same as item a-3c.
4.
The average residence time is estinated to be 14 days.
5.
The expected volume of solid wastes is as given in item a-5 except evaporator bottoms will be stored in-tanks and subsequently drummed for off-site shipment.
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c.
Laundry and hot showar decontamination and wash-down vastes are estimated to be approximately 635 gal / day with an estimated activity content of 10-5 uc/cc.
i 1.
See answer to item a-1.
2.
It is planned to discharge these wastes without processing provided the activity in the discharge canal can be maintained at 1 x 10-9 uc/cc.
If this cannot be accomplished these wastes will be processed and either discharged or reused depending upon plant makeup requirements and water quality.
3.
If these vastes arc to be proces.ed the treatment steps include:
a.
Cation demineralizer DF - same as item b-3a.
b.
Miscellaneous waste evaporator / condensate demineralizer - b-3b.
4.
Not applicable.
5.
Same as item b-5.
d.
Steam generator blowdown - not applicable to Crystal River Plant Unit 3.
Ilowever, condensate demineralizer will be used co maintain water quality
-in the secondary system.
In the event of fuel failure and primary to secondary system leakage, these demineralizers may become contaminated.
Under these conditions, it in tentatively planned to process the regenera-
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..s tion solution for these demineralizers through the miscellaneous waste disposal system.
An estimate of the quantity of this waste is 13,000 gal / day. Assuming a 10 ga'./ day primary to secondary leak and 0.1 percent defective fuel, the activity content is estimated to be 2 x 10-3 ue/cc prior to treatment.
t 1.
This waste can be directed to the miscellaneous waste storage tank in the waste disposal system (20,000 gal.).
2.
These wastes will be recycled to the secondary system or discharged depending on secondary plant makeup and water quality requirements.
3.
Thi ua:tc will be preccc=cd by creporation and deminercli tion, 4
expected DF - 10 for all isotopes.
4.
Not applicable.
1 5.
The concentrate will be handled the same as item b (dirty wastes).
e.
Turbine building drains are estimated to be 2900 gal / day. These wastes are normally non-radioactive.
In the event of a primary to sectadary system leak along with defective fuel these wastes will become contaminated.
Assuming 0.1 percent defective fuel and a 10 gpd primary to secondary Jeak the estimated activity content of this waste is 8.6 x 10-7 uc/cc. These
-wastes will normally be discharged without treatment.
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Question #33 - Dilution' flow rate for liquid effluents, normal gas and total gallons per year.
Answer:
1 The dilution flow rate for liquid effluents prior to dilution in a natural body of water (Gulf of Mexico) was assumed in the environmental report to be 680,000 gpm or 3.58 x 1011 gallons per year. The total dilution flow
,availabic in the discharge canal for all Units 1, 2 and 3 at Crystal River Plant is 1,300,000 gpm.
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