ML17037C283

Letter Responding to the September 18, 1972 Letter Requesting Additional Information Concerning Basic Data for a Source Term Calculation and for a Gaseous and Liquid Analysis

ML17037C283
Person / Time
Site:	Nine Mile Point
Issue date:	10/10/1972
From:	Brosnan T Niagara Mohawk Power Corp
To:	Muller D US Atomic Energy Commission (AEC)
References
Download: ML17037C283 (24)

Text

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FI FROM: A DATE OF DOC: DATE REC 'D LTR hSMO RPT Niagara Mohawk Power 'Corporati n Syracuse, N. Y. 13202 T. J. Brosnan 10 2 10 2 TO ~ ORIG CC hh. Muller CLASS: tl PROP INFO INPUT NO CYS REC'D DQCiKT NO:

50-220 DESCRIPTION: ENCLOSURES:

Ltr re our 9-18-72 ltr, trans the following:

Basicu33ata for a Source Term Calculation and.

for a Gaseous and. Licpd.d. analysis~ subnd.tted, in response to our 9-18-72 ltr.

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NIAGARA ~~ MOHAWK 300 ERIE BOULEVARD WEST SYRACUSE, N. Y. I3202 October 10, 1972 C P

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I CD Mr. Daniel R. Muller, Assistant Director for Environmental Projects Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 20545

Dear Mr. Muller:

Re: Nine Mile Point Unit No. 1 Docket 50-220 Transmitted herewith are 45 copies of the information requested in your letter of September 18, 1972.

Arrangements have been finalized to meet with repre-sentatives of Oak Ridge National Laboratory on October 20, 1972, to discuss this material.

Sincerely,

. J. Brosnan Vice Pre dent and Chief Engineer TJB/vk Enclosures DOCK~

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UESTION 1 Reactor power (MWt) and plant capacity factor (%) at which impact is to be analyzed.

ANSWER The licensed reactor power at which impact is to be analyzed is 1850 MWt. The capacity factor for the unit is 85 percent.

(Environmental Report Section 9)

UESTION 2 Weight of U loaded (first loading and equilibrium cycle).

ANSWER The initial core contained 227,577 lbs. of uranium. The equilibrium cycle will depend on the annual capacity factor, and the then current design practices. It is anticipated that the uranium loading for equilibrium cores will not differ significantly from that of the initial core.

UESTION 3 Isotopic ratio in fresh fuel (first loading and equilibrium cycle).

The initial core contained an average of 2.1% U-235 (as measured) as compared with the 2.12% design value reported in the PSAR (Volume I,Section IV, Page 4). Equi, librium reload fuel is expected to contain an isotopic ratio in the range of 2.58 w/o U-235.

UESTION 4 Expected offgas rate after 30 minutes delay.

ANSWER The expected offgas rate after 30 minutes delay is less than 50,000 mCi/sec. (Ref. Environmental Report Table 3.6-1, Sec. 3.6.3.3, 3.6.3.5.1)

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Escape rate coefficients used (or reference).

ANSWER Noble Gas Release Rate (1) R = 2.6x10 y Ji '1-e ) (e )

Halo en Release Rate

.(2) R = 2.4x10 y R '1-e 0.5

-4'alo

) (e )

en Reactor Water Concentration (3) c V ( +++'() P Where:

R i = Release rate of isotope (wCi/sec)

Y = Fission yield of isotope i (atoms/fission)

-1 i = Decay constant of isotope i (sec )

T = Fuel irradiation time (sec) t = Decay time following release from fuel (sec)

C = Concentration of isotope i in reactor water (~Ci/g)

Volume of water in operating reactor (cc)

-1 Cleanup system removal constant (sec )

Cleanu s stem flow rate /sec 8 = Quantity of water in operating reactor (g)

-1 Steam carryover removal constant (sec ) for halogens 0.01 Y= Quantity steam flow /sec of water in operating reactor (g)

= Density of water in an operating reactor = 0.74g/cc Noble Gas Release Rates The release rate of noble gases can be expressed by the simplified form of Equation (1):

R g

= Kyk g

The observed experimental data have shown a variation in individual noble gas isotopes with respect to each other that can be expressed in terms of variation in m, the exponent of the decay constant term (g). The average measured value of m was 0.4 with a standard deviation of%0.07. With the$ R at 30 min set at 50,000~Ci/sec, the value of Kg is selecting the value of m.

calculated'fter Halo en Release Rates The release rate of halogens can be expressed by the simplified form of Equation (2):

R n

= KYA, n

The observed experimental data have shown a variation in individual halogen isotopes with respect to each other that can be expressed in terms of variations in n, the exponent of the decay constant term ( A) . The average measured value of n was 0.5 with a standard deviation of ~0.19. With I-131 release rate set at 700~Ci/sec, the value of Kn is calculated after selecting the value of n.

UESTION 6 Mass of primary coolant in system (lb).

a. Mass of primary coolant in reactor; mass water; mass steam (lb).

b. Mass of primary coolant in recirculating system (lb).

c. Fraction of primary coolant in main condenser (lb).

ANSWER

a. Mass of water in reactor 379,400 lbs.

Mass of steam in reactor 11,600 lbs.

b. Mass of primary co'olant in recirculating system 90,500 lbs.

c. Mass of primary coolant in the main condenser is 918,000 lbs. This is approximately 5/8 of the total primary coolant inventory excluding the condensate system, the feedwater system upstream of the isolation valve, the main steam system downstream of the second isolation valve, the turbine and the condenser steam space.

1 Steam conditions, at turbine (temp F, press psi, flow lb/hr).

ANSWER flow, lb/hr* 7.25xlO 6 pressure, psia 965 538

• Includes 5,000 lbs/hr air ejector motive steam and 410,000 lbs/hr steam flow to reheat.

UESTION 8 Normal recirculation flow rate (lb/hr).

ANSWER Normal recirculation flow through the core at the-design rating is 67.5x106 lbs/hr. This figure includes both circulation and feedwater flow.

UESTION 9 Normal clean-up system flow rate (lb/hr). What type of resins are used? What decontamination factors are expected for each principal nuclide? What is the frequency of regeneration and volume of regenerants?

ANSWER The normal flow through the reactor water clean-up system is 300,000 lbs/hr. The design flow is 380,000 lbs/hr. The ion exchange resin is a mixture of cation and anion resins (amberlite 200 and IRA 900).

The resins are 2 to 1 by volume, cation to anion. While the individual radionuclide decontamination factors have not been deter-mined> the overall decontamination factor is expected to be at least

10. Operationally, experience has demonstrated that regeneration of the clean-up demineralizer resins is not practical. Therefore, these resins are removed after a service life of about six months.

UESTION 10 Describe and provide the expected performance of the expanded gaseous radwaste treatment system from the main condenser air ejector? Give the expected air in leakage. Is the condenser ejector one stage or two stage? Where is it discharged? How many condenser shells' (If applicable pounds of charcoal and operating temperature F)

ANSWER The hold-up portion of the offgas system will be a charcoal base system designed to provide hold-up times of 20 days for xenon isotopes and 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for krypton isotopes based on an air (condenser.air inleakage) flow rate of 22 cfm. Since the air inleakage is expected to be approximately 10 cfm maximum, the expected offgas system hold-up times would be approximately twice the design values given above. The condenser air ejection system is a two-stage design that dis-charges to the offgas system. There is one condenser shell.

The calculated quantity of charcoal required is 85,000 lb. at 77 F.

What is the expected leak rate of primary coolant to the drywell (lb/hr)? How frequently is the drywell purged? What treatment is given to this purge and where is it released?

ANSWER The leak rate of primary coolant to the drywell is estimated to be 5.5 gpm (2750 lb/hr) (FSAR, Fifth Supplement, P-18). This leakage is from the recirculation pump seals and from valve stem packing.

It is not expected that the drywell need be vented and purged on a routine basis during normal operation. The containment will be purged during each startup with pure nitrogen until the atmosphere contains less than five percent oxygen. The containment will be deinerted during reactor shutdown for maintenance and/or refueling (i.e. approximately once per year). Gases from the containment are normally exhausted directly to the stack by a fan rated at 10,000 cfm. However, the gases can be routed through the reactor building emergency ventilation system if necessary.

UESTION 12 What is the expected leak rate of primary coolant (lb/hr) to the reactor building? What is the ventilation air flow through the reactor building (cfm)? Where is it discharged? Is the air filtered or otherwise treated before discharge? If so, provide expected performance.

ANSWER The expected leak rate of primary coolant to the reactor building is negligible. Most leakage is identified (such as pump seal, valve packing, etc.) and goes to closed equipment drains. Very little, if any, of these find their way into the reactor building atmosphere.

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Floor drain leakage has been averaging on the order of 1.0 gpm.

However, the amount of primary coolant in this water is very small (about lx10 3 gpm based on activity analysis).

The normal ventilation air flow through the reactor building is 35,000 cfm which is discharged to the stack. The exhaust is not treated, but radiation monitoring is provided. A maximum flow of 70,000 cfm can be reached with high speed purging.

UESTION 13 What is the expected leak rate of steam (lb/hr) to the turbine building? What is the ventilation air flow through the turbine building (cfm)? Where is it discharged? Is the air filtered or treated before discharge? If so, provide expected performance.

ANSWER The leak rate of steam to the turbine building is not expected to exceed 7 gpm or 2,610 lb/hr. (Environmental Report, Sec. 5.2.5.2)

The ventilation exhaust system has two fans. The fans are inter-locked so that only one can operate at a time. The normal ventilation air flow through the turbine building is 170,000 cfm, which is discharged to the stack. The normal exhaust is not filtered or otherwise treated before being discharged.

UESTION 14 Describe the treatment of the exhaust stream from the turbine seal glands.

a. What is the origin of the steam used in the gland seals'? (i.e.,

is it primary steam condensate, or demineralized water from a separate source, etc.?)

b. How is the waste stream from the gland sea1s treated and disposed of'

c. Indicate how often the mechanical vacuum pump will be operated and the expected range of activity released.

ANSWER

a. The origin of the steam used for the turbine gland seals is primary reactor steam.

b. The steam from the packing exhausters is condensed and the air and gases that remain are sent through a 1.75 min holdup pipe. The holdup pipe discharges to the stack where it is diluted with ventilation air.

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C~ The mechanical vacuum pump system is provided for hogging air from the condenser prior to starting the turbine. The system is employed after each refueling and maintenance outage, which are annual events, and at such other extended shutdowns which may be necessitated in the interim. Over the life of the unit, these additional shutdowns should not, average more than one per year. The amount of activity released depends to a large degree upon the preshutdown offgas release rate, the type of fission product mixture, the duration of the shutdown, and the length of time required to evacuate the condenser'. Further, the activity release tends to peak within the first few minutes of hogging operation and decays substantially thereafter. Considering these factors, the release rate over several hours of hogging operation might average out to be in the same range as the preshutdown offgas releases.

UESTION 15 Provide average gallons/day and >Ci/cc prior to treatment for the following categories of liquid waste. Use currently observed data in the industry where different from the SAR or Environmental Report (indicate, which is used).

aa High-purity wastes (for example, "clean" or low conductivity waste and equipment drains). Give range of activity expected.

b. "Dirty wastes (for example, floor drain wastes, high-conductivity wastes, and laboratory wastes). Give range of activity expected.

C ~ ,Chemical wastes. Give range of activity expected.

d. Laundry, decontamination, and wash-down wastes. Give range of activity expected.

For these wastes (a-d),'rovide:

aa Number and capacity of collector tanks.

b. Fraction of water to be recycled or factors controlling decision.

c ~ Treatment

,principal steps-include nuclide controlling decision.

for each step. 'f number, capacity, and process D. F. for each step is optional, state factors

d. Decay time for primary loop to discharge.

ANSWER This response is based on information contained in the Environmental Report.

Gallons/ Activity ~Ci/cc a ~ Hi h- urit Wastes ~da Max.

Equipment drains 63,000 0.11 Condensate demin. rinse 2,500 0.025 URC Wash water 1,500 0.045 Waste concentrator distillate ,4,000 0.0058 5

Drywell floor drains 1,000 2 X 10

b. Dirt Waste I Floor drains 4,000 0.0026 Centrifuge Effluent 1j300 0.0001 Laboratory Drains 500 0.001 Concentrator Rinse 50 0.1

Gallons/ Activity ~Ci/cc

c. Chemical Wastes ~da Max.

Regenerant Chemicals 1>000 3.0

d. Laund Decontamination and Wash-Down Wastes Laundry wastes 300 (1X 10 Decontamination drains 50 1.0 For these wastes (a-d), provide:

a. Number and capacity of collector tanks.

Size No. Gallons

1. High purity wastes collector tanks 257000

2. Dirty wastes collector tanks 10,000

3. Chemical wastes neutralizing tanks 15,000

4. Both 1 6 2 above can overflow to waste surge tank 50,000

5. Laundry drain tanks 10,000

b. Under normal operating conditions, approximately 96 percent of the waste liquid is expected to be recycled for reuse within the unit.

The fractions which will be recycled are as follows:

1. Equipment drains, condensate demineralizer rinse, URC wash water, waste concentrator destillate, drywell floor drains 97% of this water is expected to be recycled.

2. Floor drains and centrifuge effluent about 50% of this waste will be recycled.

3. Regenerant chemicals, laboratory drains, concentrator rinse, decontamination drains all of this waste, water is expected to be recycled.

4. Laundry wastes 100% discharge.

c. Treatment Steps

1. High purity waste a) Waste Collector Filter 1 capacity 300 gpm decontamination factor 5 b) Demineralizer 1 capacity 300 gpm decontamination factor 1000

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2. Dirty waste a) Floor drain filter 1 capacity 300 gpm decontamination factor 5 b) Traveling belt filter - 1 capacity - 40 gpm decontamination factor 5 c) Waste evaporators 2 capacity 81-12 gpm, ./f2-20 gpm" decontamination factor 81-500, //2-300,000*

The floor drain filter, traveling belt filter and waste evaporators for handling the dirty waste will be at the option of the operator. The evaporators may also be used for chemical wastes below.

3. Chemical wastes Waste evaporators described above

d. Decay time from primary loop to discharge is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, minimum.

• Upgraded System as described in Environmental Report, Sec. 3.6.3 UESTION 16 For the condensate demineralizers provide the flow rate (lb/hr), type of resin used, expected backwash, and regeneration frequency, and expected D. F. for each principal nuclide.

ANSWER The desig~ flow rate for the condensate demineralizer system is 7.25 x 10 lb/hr. Since five demineralizers are in service, (and one standby) each one is expected to pass 1.45 x 106 lb/hr. The resins are of the mixed bed type (amberlite 200 and IRA 900) and consist of 2 to 1, by volume, cation to anion. Each demineralizer is regenerated on a frequency of approximately every six weeks. An ultrasonic resin cleaner will be installed at the station. It is expected that this equipment will decrease the frequency of regeneration so that each demineralizer will be regenerated approximately every six months.

Backwashing is not presently employed since it has proven to be of little value. Although the expected decontamination factor for each nuclide is not available, the design basis for the condensate deminer-alizer system is such that essentially 100 percent removal efficiency for all principal fission and corrosion/activation products may be assumed.

UESTION 17 Dilution flow rate for liquid effluents, minimum and normal gpm and total gallons per year.

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ANSWER The normal dilution flow rate is 268,000 gpm. The minimum flow is approximately 18,000 gpm (service water flow). Assuming an 85 percent capacity factor for the unit, the total dilution flow per year would approach 120 billion gallons.

UESTION 18 How is waste concentrate (filter cake, demineralizer resin, evaporator bottoms) handled'7 Give total volume or weight and curies per day or year. Include the expected annual volume of dry waste and curie content of each drum.

ANSWER Filter sludge is dewatered, transferred into containers, and shipped offsite for disposal. Filter cake from the traveling belt filter is discharged into drums, stored, and shipped offsite for resins are flushed to processing facilities, dewatered, loaded disposal.'pent into containers, stored, and shipped offsite for disposal.

Concentrates (evaporator bottoms) are cooled prior to transfer to the packaging facilities, mixed with an absorbent, loaded in containers, stored, and shipped offsite for disposal. (Ref. Environmental Report, Sec. 3.6.4.2)

Solid Radwaste No. of Volume Total curies No. of Ci per

~Shd ments ~Shd ed Based on input from Jan. 1, 1971, to 44 12,910 ft. 201.21 1,756 0.115 Dec. 31, 1971

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