ML20127K324

Forwards Info Re Liquid Waste Concentrations & Cooling Water Requirements for Plant Prepared in Accordance W/Hl Price 680529 Direction

ML20127K324
Person / Time
Site:	Monticello
Issue date:	05/31/1968
From:	Howe P US ATOMIC ENERGY COMMISSION (AEC)
To:	Price H US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9211200373
Download: ML20127K324 (7)

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f .e O' May 31, 1968

/ I TO: .. Harold L. Price -

Director of Regulation FROM: P. W. Howe,. Asst. Chief. Environmental & Radiation Safety Technology Branch, DRL hh%

Attached information regarding liquid waste concentrations and cooling water requirements for the Monticello Nuclear l Generating Plant was prepared-in accordance_with Mr.-Price's direction'of-May 29, 1968. l Additional information is also included-for the Northern States Power Company's Prairie Island Nucicar Generating Plant'.

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. F. Western-P. Morris S. Levine L. Rogers I

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MONTICELLO NUCLEAR GENERATING PLANT 1674 mkt - P,0ILING WATER RFACTOR

1. Percent of river _ flow used for cooling River Flow Average = 4800 cfs Minimum = 240 cfs Maximum - 54,000 cfs Intake, 972 cfs without cooling towers 54 cfs full cooling tower recycle l

Percent Intake Average flow - no towers - 22%

Maximum flow - no towers - 1.8%

Average flow - tower recycle - 1%

Maximum flow - tower recycle .1%

Minimum flow - tower recycle - 22%

II. Anticipated Radioactive Liquid waste effluent concentrations at outfall:*

Concentration will vary with the use of cooling towers.

Operation without cooling tower

-9 Normal operation - concentration = 10 ue/cc

-8 Fuel Failure - concentration = 10 ue/cc

• Not including tritium.

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1 Operation - 100% recycle on cooling tower

-8 Normal operation - concentration = 10 uc/cc

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, Fuel Failure - concentration = 10 uc/cc Based on presentation given before ACRS, May 5, 1966.

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MPC for unknown mixer = 10 uc/cc

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MPC for anticipated isotopic composition of effluent = 10 ue/cc Ill. Principal Isotopes anticipated in liquid waste effluent - Based on Dresden 1 experience.

Isotope Concentration uc/cc at 10 -7 ue/cc

• -8 Ba 140jg,140 2.4 x 10 Sr 1.9 x 10 -8 90

Sr 8.0 x 10 -30 134 -8 Cs 1.1 x 10 1

Cs 2.1 x 10 -8 38 Co 9.0 x 10 ~9 60 Co 3.8 x 10 ~9 144 Ce 5.2 x 10 -9 Zr95/Nb 95 9

-9 131 1 3,0 x 30 -11 4

The concentrations are also based on a stack release of 0.3 c/see which might not in fact be the release limit for this plant. This will be determined during the POL review.

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IV. Calculated concentrations at the Minneapolis Muncipal Water Intake

• Assuming a concentration of 6 x 10~7 uc/cc in the river at the plant

~0 site during annual average flow and a concentration of 3.6 x 10 uc/cc during annual minimum flow the resulting concentration at the

~0 Minneapolis municipal water supply intake would be 3.6 x 10 uc/ct

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for average flow period and 1.8 x 10 uc/cc during minimum f1pv period.

Discharge concentrations are anticipated to be significantly below the values used for this analyses.

V. Anticipated Tritium production in the Monticello reactor Sources: a. Tritium formed from neutron bombardment of deuterium present in water.

b. Fissioning process. .

Rate of formation:

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H is formed from the deuterium reaction at a rate of 4.7 x 10 ue/sec and from fissioning at the rate of 165 ue/sec. The Tritium formed during fissioning is within the fuel rod and must escape either by diffusion through the clad or from failed fuel performations. Diffusion of Tritium through Zirconium clad is estimated to be less than 1%.

Anticipated effluent concentrations:

Based on the stated rate of fotmation and assuming total release of the Tritium produced by the determined reaction and the fissioning (100%

(Based upon applicant's hydrological medel for dilution in the Mississippi River).

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diffusion) the concentration at the outfall vould be approximately 8 x 10 -6 uc/cc which is .2% of MPC. The use of 100% diffusion of Tritium through Zirconium clad is extremely conservative and if one were to use the more acceptable value of 1% the Tritium concentration at the outfall would be .002% of MPC.

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1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1720 m.T-PRESSURIZED k'ATER REACTOR (BOTl! UNITS)

luotope lialf-life Fraction of Annual Annual ( )

(Days) ;PC(2)

RcIcase.cc Averahe Con-con:rsticu uc/cc MS 54 300 3.3 x 10 ~11 2.0 3.3 x 10 ~10

'.N 56 300 9 x 10-10 5.4 x 10 1 9 x 10~14 CO 58 72 1.1 x 10 ~9 6.0 x 10 1 1x10 ~13

, CO 60 1900 4x10 ~1 7.1 1.2 x 10 ~10 SR 89 50.5 1.1 x 10~8 1.9 x 10 1 3.2 x 10 ~14 SR 90 6.6 x 10 ~E 10,000 1.2 x 10 1 2 x 10 ~1 Y 90 2.65 1.8 x 10 -10 2.2 3.7 x 10 -15 L' 91 0.4 1.7 x 10 -10 5.1 6.5 x 10-15 Y 91 56 2 x 10 ~9 4.3 x 10 1 7.2 x 10~14

Y 92 0.15 3 x 10-10 1

7,3 10 1.3 x 10 ~14 h3 99 2.79 11e 10

-6 2.6 x 10' 4.3 x 10 -11 I 131 0 7.7 x 10 -5 1.4 x 10 2.3 x 10~11 Tr. 132 3.2 1 x 10'I 1.4 x 10 3 2.3 x 10~1 I 132 0.1 1x 10 ~7 5.7 x 10 9.5 x 10-13 1 133 0.C7 1.8 x 10 -5 1.1 x 10 4 1.C x 10 -11 i

1 134 0.036 3 x 10~9 4.4 x 10 1 7.3 x 10 ~1' CS 134  !

S40 3.3 x 10~7 1.3 x 10 3 3 x 10~1  !

CS 136 13 5x 10 ~9 -1.7 x 10 2.3 x 10 ~13 CS 137 11,000 7.5 x 10

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9.3 x.10 1.5 x 10 -11 1

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AL"JAL RELi:ASL, E0711 L' NITS (CONT'd.)

A::r.ual Aver.v.c Con =

1. 1. U ### "

Isotopo Half-life Fraction of Annual (Days) tiPC } * #"# ' "#

I EA 140 12.8 4 x 10

~10

!. 6 7.7 x 10 -15 LA 140 1.7 4 x 10 -10 4.3. ^ x 10 ~1$

CZ 144 290 2.5 x 10 -9 1.E x 10 1 2.5 x 10 -10 11 3 4500 1.5 x 10 ~3 2.67 x 10 9 4.45 x 10-6 I

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i (1) l Based on annual circulating dischargo canal flow of 6 x 10 ' cc/ycar l Most restrictive FTCv, Part 20 l

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