ML20087D075

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Rev 4 to Offsite Dose Calculation Manual
ML20087D075
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 11/14/1984
From: Sorenson J
NORTHERN STATES POWER CO.
To:
Shared Package
ML20087C965 List:
References
PROC-841114, NUDOCS 8403130278
Download: ML20087D075 (11)
v • d • e


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PRAIRIE ISLAND NUCLEAR GENERATING PLANT jJ CHANGES TO OFFSITE D3SE CALCULATION MANUAL (ODCM)

TABLE 5.1-1 RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS In accordance with the Prairie Island Technical Specifications Section 6.5 E, Offsite Dose Calculation Manual (OCDM), a change to Figure 5.1-1 and Table 5.1-1 Radiation Env_ironmental Monitoring Program, Sarpling Location is submitted.

One of three dairy farms required by the sampling program is located 3.5 miles at 181*/S from!the facility. The dairy farm owner has decided to move his operation to another location. ,

After. consulting the Dispersion Parameters (0/Q)'in the Offsite Dose Calculation Manual, the ' decision-was made to sample ' raw milk from the Perry Christensen Farn located 3.7 miles at 88'/E of the plant, the next highest D/Q farm.

LIQUID RELEASE DILUTION FLOW ,

Setpoint calculations were' originally based on a dilution flow of 4.52E5 GPM (1000 CFS). This method took credit for Sturgeon Lake dilution. This method is no longer

-correct since circulation' discharge no. longer is diluted into Sturgeon Lake prior to entering the main body of the Mississippi due to plant modifications. Minimum ,

dilution flow of 67,300 GPM (150 CFS) yields conservative'results.

Instructions for Entering Rev. 4 to the Prairie Island ODCM

1. Remove 00CM cover page and pages y, vi, 2.2, 2.5, 5.2 and 5.6.
2. Replace-00CM cover page'and pages v, vi, 2.2, 2.5, 5.2 and 5.6 with Rev 4 pages. (Pages 2.2 and 2.3, 2.4 and 2.5, 5.5 and 5.6 are printed on a
single sheet).
3. Use 00CM page vi to page check your manual if desired.

. 8403130278 840301 i PDR ADOCK 05000282

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E 022784G0W01

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL

. .e (ODCM)

REV.4 DOCKET NO. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA OPERATIONS COMMITTEE FINAL REVIEW DATE: //- -h3 REVIEWED BY: om -

DATE: /////

,/s 3 APPROVED BY: p DATE: /[/h

ECORD OF EVISIONS Revision !4o. Data Reason for Revision Original June 7,1979 -

1 April 15. 1980 incorpcration of !fRC Staff comments and correction of miscellaneous errors 2 Aug 6,1982 Incorporacioa of NRC Staff comments -

3 Feb 21, 1983 Change in milk sampling location 4 .- Nov. 14 1983 Change in milk sampling location and change in cooling tower blowdown

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v Rev. 4

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4 I

LIST OF !?TEC"JTVE PACES Psee Nou Revision No. Pare L. Revision 7.

Cover 4 3-11 2

'i 2 3-12 0 11 1 3-13 2 tii 0 3-14 2 iv 0 3 -15 2 v 4 3-16 2 vi' 4 3-17 0 1-1 1 3-18 1 2-1 2 3-19 0

2-2 4 3-20 2 2-3 2 3-21 2 2-4 1 3-22 2 2-5 4 3-23 2 2-6 1 3-24 2

2-7 2 3-25 2 2-7a 2 3-26 2 2-8 2 3-27 2 2-9 0 3-28 2 2-10 2 3-29 2 2-11 2 3-30 2 2-12 2 3-31 2 2-13 1 3-32 2 2-14 2 3-33 2 1 2-13 2 3-34 2 3-1 2 3-35 2 3-2 1 3-36 2 3-3 1 3-37 2 3-4 2 3-38 2 3-5 2 4-1 1 3-6 1 4-2 0 3-7 1 4-3 0 3 2 .5-1 1 3-9 2 5-2 4 3-10 2 5-3 2 5-4 1 5-5 1 5-6 4 5-7 2 5-8 1 A-1 thru 0 A-39 B-1 .-Aru O 3-8 C-1 thru 2 C-14 v1 Rev. 4

7 ,7.__.

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2.1.1.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.

a. Determine the liquid source terms that are representative of the " mix" of the liquid effluent. Liquid source terms are the totti curies of each isotope released during the previous month. Table 2.1-1 source terms may be used if there have been no liquid releases.
b. Determine Si (the fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i") for each individual radionuclide in the liquid effluent.

S Ai i=)[A i (2.1-1) i Ai = The radioactivity of radionuclide "i" in the liquid effluent ,

2.1.1.2 Determine C t (the maximum acceptable total radioactivity concentration of all radionuclides in the liquid effluent prior to dilucion (gCi/ml)).

Ct" f __S i (2.1-2)

MPCi i

F = Dilut' ion water flow rate (gpm)

= 67,300 gpm from cooling tower blowdown f = The maximum artalnable discharge ficw rate prict to dilution (gpm) 2-2 Rev. 4 l

.. .. . 2 . ; = :. -- . .. - = - . = .= v .-- - .. .:-- -

'l ,-

= 60 gym from the ADT tank pump (2) .

= 100 gym f rom - the CVCS tank pump (2) ,

= 60 gym'from the SGBD tank pump (2)

MPCi = The liquid effluent radioactivity concentration limit for radionuclide "i" (gCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1, obtained from Rererence 3.

2.1.1.3 Determine Cm (the maximum acceptable total radioactivity concentration o'f the radionuclides (minus tritium) in the liquid discharge prior to dilution (sci /rl)) .

l

'Ca = Ct- (CtHS ) (2 1-3)

SH = The fraction of the total radioactivity in the liquid effluent contributed by tritium and other -

radionuclides that do not emit gamma or X-ray

. radiation. .

2.1.1.4 Determine C.R. (the calculated monitor count rate above nacxground attributed to the radionuclides (nepm)) .

C.R. is obtained by using the applicable Effluent Monitor Ef fic-iency Curve located in the Radiation Monitor Calibration file.

C.R. is the count-rate that corresponds to the " adjusted" total racioactivity concentration (Cm)-

1 2-3 Rev. 2

(- .a. .- -

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2.1.1.5 Determine USP (the monitor high alarm setpoint above I

nacxground (ncpm)).

ESP = TmC.R. (2.1-4)

Ta =' Fraction of the radioactivity from the site that may be released via each release point to ensure that the site coundary dose rate limit is not exceeded due.to simultaneous releases from severaI release points.

= 0.90 for the Waste Effluent Liquid Monitor (R-18)

= 0.05 for the Staam Generator Blowdown Liquid Monitor - Unit 1 (lR-19)

, = 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19)

Tm. values may be revised from the values given above.

The summation of all the Tm values shall not be greater than unity.

2.1.1.6 The monitor high alarm setpoint above background (nepm),

shall be set at or below the HSP value.

2.1.2 Setooint Based on Analvsis of Liquid Prior to Discharce (optional)

This' method may be used in lieu of the method in Section 2.1.1 te determine the setpoints for the maximum acceptable discharge flow rate prior to dilution and to determine the associated high alarm setpoint based on this flow rate for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Monitor - Unit 1 (1R-19), and Steam Generator Blowcown Liquid Monitor - Unit 2 (2R-19), during all operational conditions.

1

2-4 Rev. 1

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2.1.2.1_ Determine .f (the maximum acceptable discharge flow rate prior to dilution (gpm)).

f , 0.8 F T.

Ci (2.1-5)

MPCi i

F = Dilution water flow rate (gpm)

= 67,300 9pm from cooling tower blowdown.

Ci = Concentration of radionuclide "i" in the liquid effluent prior to dilution (#C1/ml) from analysis of the liquid effluent to be released.

MPCi =,The liquid effluent radioactivity concentration ~

limit for radionuclide "i" (#Ci/ml) from Table

^2.1-1 or if not listed in Table 2.1-1 from Refer-ence 3.

Ta Fraction of the radioactivity ~from the site that -

may be :aleased via each release point to ensure that the site boundary limit is not exceeded due l to simultaneous releases from several release l points. Refer to Section 2.1.1.5.

I 2.1.2.2 Determine the monitor setpoint based on the radionuclide mix of the liquid effluent.

a. Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (ncpm)).

L C.R. is obtained by using the applicable Effluent Moni-tor Efficiency Curve located in the Radiation Monitor 2-5 Rev. 4 I

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YASLE 3.1-1 PRAIRIE ISLAND NLJCLEAR CENERAT4NC PLANT RADIATION ENVIRONMENTAL MONITORING PRCCRAM SAMPLING LOCATIONS ,

Type of

_Samole Coce Collection site Locati--

River Water C P-3 Upstream of Plant River Water 0.6 zu @ 6G lENE P-6 Lock & Dam #3 0 Drinking Water 1.6 mi @ 129 /SE P-11 City of Red Wing Well Water C 7.1 mi @ 133*/SE P-23 Kinneman Farm Well Water  !!.1 mi @ 331*/NNw P-6 Lock & Dam #3 Well Water 1.6 mi @ 129"/SE P-8 Kinney Store 2.0 mi @ 21',*/W Well Water P-9 Plant Well #2 0.3 mi @ 306*/NT Sesiment-River P-3 C Upstream of Plant 5ediment-River 0.6 mi @ 60 /ENE P-6 Lock & Dam #3 8 t.6 mi @ 229 /55 Sealment-Shoreline P-12 .

Recreation Area s Perinhvton or c 3.4 mi @ 116*/ESE P.S Upstream of Plant Macroinverteorates P-6 0.6 mi @ 60*!ENE Lock & Dam v3 1.6 mi @ 129*/SE Fish P-3 C Upstream of Plant 0.6 mi @ 6",*/ENE Fish P-6 Lock & Dam #3 1.6 mi @ 129*/SE Milk P-25 C Kinneman Farm 11.1 mi @ 331 [NNT Milk P-14 Gustafson Farm 2.2 mi @ 161*/SSE Milk P-16 Johnson Farm - 2.6 mi @ 600'/ENE Milk P-17 Place Farm 3.5 m @ 25 /NNE

! Milk P-11 l

Christettsen Farm 3.7 m8 @ 88 /E l

l r.

1 l

3-2 Rev. 4

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\( , TABLE 5.1-1 (continued) ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM i

5AMPLING LOCATIONS TYM "f .

~

3 amole Code CoIIection Site Location Direct Radiation (TLD) P065 Earl Flynn Farm 2.5 ml @ 299*/ TNT Direct Radiation (TLD) PO'1C Robert Minneman Farm 11.1 mi. @ 331*/NNW A

"c" denotes control location'. All other locations are indicators.

The letters after numbered TLC's are as follows:

"A" denotes locations in the general area of the site boundary

. B" denotes locations about 4 to 5 miles distance from the plant "5" denotes special Interest locations.

k_ 5-5 Rev. I L

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