ML20211G039

Revised ODCM, Including Revs to Revised ODCM Index,Odcm 01.01 Page 2 Paragraph 1,ODCM 02.01 Page 2 Section 1.0,ODCM 05.01 Page 2 Sections 1.0,2.0 & 3.0 & ODCM 13.05 Page 2

ML20211G039
Person / Time
Site:	Monticello
Issue date:	02/10/1999
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20211G002	List: ML20211F996 ML20211G011 ML20211G021 ML20211G039
References
PROC-990210, NUDOCS 9908310135
Download: ML20211G039 (26)

Text

-_ _---

- ODCM REVISION December 1998 Section Revision and Reason 01.01 page 2 paragraph 1 Changed 10CFR50.361 to 10CFR50.36a , corrected typo.

02.01 page 2 section 1.0 Changed table reference from 2.1-2 to 2.1-1, corrected reference.

05.01 page 2 sections 1.0, Changed word " waste" to " effluent" in section 1.0, 2.0, 3.0 changed 1" sentence in section 2.0 to exact wording in T.S., added section 3.0 to reference section 1.0 word change to LAR 39.

13.05 page 2 Changed sample collection site resulting from annual .

land-use census.

9908310135 990826 PDR ADOCK 05000263 C ; .. . R m..... .

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fONTICELLO NUCLEAR GENERATING PLANT ODCM-lNDEX TITLE: OFFSITE DOSE CALCULATION MANUAL Revision 2 INDEX Page 1 of 1 l l

// .n / , REVIEW AND APPROVALS Prepared By: ///th/ N d /[i/pl d T;/(' , ,

Approved By: [/M gjj Effective Date: g/b/487 Resp Supv: CHEM I Assoc Ret- CHEM MAN 1 MSR: N lFreq: 0) yrn ,

ARMS: ODCM-INDEX l Doc Tvoe: 7030 l Admin Initials: \ l #- IDateAll D l( / h l

SECTION TITLE l ODCM-01.01 Introduction ODCM-02.01 Uquid Effluents ODCM-03.01 Gaseous Effluents ODCM-04.01 Information Related to 40 CFR 190 and 40 CFR 141

]

ODCM-05.01 Radiation Environmental Monitoring Program '

ODCM-06.01 Meterological Analysis ,

ODCM-07.01 Monticello 10 Meter Wind & T42.7-10 Meter Stability Joint Frequency '

Distribution 09/01/76 to 08/31/78 ODCM-08.01 Monticello 100 Meter Wind & T100.10 Meter Stability Joint Frequency Distribution 09/01/76 to 08/31/78 ODCM-09.01 Summary of EBARR Computer Program ODCM-10.01 Methodology for Computation of Dose Parameters for Radiciodines, Particulates and Tritium .

ODCM-11.01 Midas Program Descriptions )

ODCM-12.01 ODCM-01.01 Figures  !

ODCM-12.02 ODCM-02.01 Figures ODCM 12.03 ODCM-03.01 Figures ODCM-12.05 ODCM-05.01 Figures ODCM 12.09 ODCM-09.01 Figures ODCM-12.11 ODCM-12.01 Figures ODCM-13.01 ODCM-01.01 Tables 1 ODCM-13.02 ODCM-02.01 Tables ODCM-13.03 ODCM-03.01 Tables ODCM-13.04 ODCM-04.01 Tables ODCM-13.05 03'js-05.01 Tables ODCM-13.06 ODCM-06.01 Tables ODCM-13.07 ODCM-07.01 Tables ODCM-13.08 ODCM-08.01 Tables ODCM-13.09 ODCM-09.01 Tables ODCM-13.10 ODCM-10.01 Tables ODCM-13.11 ODCM-11.01 Tables I/cjs

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-01.01 TITLE: INTRODUCTION Revision 1 l r Page 1 of 2 Prepared By:

h Reviewed By: ,f;hp 4 OC Final Review Meeting: h 8/fA Date: /d.//o/ff Approved By:

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-01.01 TITLE: INTRODUCTION Revision 1 f

Page 2 of 2 This Off-Site Dose Calculational Manual (ODCM) provides the information and methodologies to be used by Monticello Nuclear Generating Plant (MNGP) to assure l

compliance with MNGP's operating technical specifications related to liquid and l

' gaseous radiological effluents. They are intended to show compliance with 10CFR 20, 10CFR 50.36a,10CFR 50, Appendix A (GDC 60 & 64) and Appendix 1, and l 40 CFR 190.

I This ODCM is based on " Radiological Effluent Technical Specifications for BWRs I (NUREG-0473, Draft),"" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133)," and other inputs from the Nuclear Regulatory Commission (USNRC). Specific plant procedures for implementation of this manual are provided elsewhere. These procedures will be utilized by the operating staff of MNGP to assure compliance with the technical specifications. .

1 Also included in this manual is information related to the Radiological Environmental Monitoring Program (REMP) in the form of Figures 5.1-1,5.1-2,5.1-3, and Table 5.1-1.

These figures and table designate specific sample types and locations currently used to satisfy the technical specification requirements for the REMP. They are subject to change based on the results of the periodic land use census.

Calculations described in this manual may be performed using computer programs designed to implement these algorithms. In addition, the current meteorological data and yjQ data may be generated by the MIDAS programs. MIDAS programs implement _

the regulatory guidance found in Regulatory Guide 1.109,1.23 and 1.111.

MIDAS is a set of programs designed to collect and process meteorological data', l radiological release data and other data to permit prompt reporting of off-site radiological consequences during emergency release conditions. MIDAS algorithms may be used when appropriate to perform dose calculations from routine airborne releases, for computation of doses from liquid releases, and to identify critical receptors.

Regulatory Guide 1.21 defines abnormal releases as " unplanned or uncontrolled release of radioactive material from the site boundary."

MNGP further defines abnormal gaseous releases as any gaseous release where the effluent release rate significantly exceeds an established normal release rate.

Abnormal releases as stated above will typically be due to personnel error, procedure inadequacy, training deficiency, or equipment malfunction.

This ODCM has been prepared as generically as possible in order to minimize the need

• for future revisions. Some changes to the ODCM will be needed in the future. Any such changes will be properly reviewed and approved as indicated in the Administrative Control Section of the MNGP Technical Specifications.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01  !

TITLE: LIQUID EFFLUENTS Revision 1

\

1 Page 1 of 15

- l Prepared By: ([ L I Reviewed By: gh [p_ l OC Final Review Meeting: h c1 / f c% Date: /c1[/o[9g Approved By: gj ,

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ARMS: OOCM-02.01 l Doc Type: 7030 l Admin Initials: 4g Date@flhlL/4)

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 I'

Page 2 of 15 It is MNGP's policy to make no routine liquid releases, however, in the event of a i release this section is used to:

l l A. Determine alarm setpoints for liquid monitors; B. Determine that liquid concentrations in effluents are below the allowable concentrations given in 10 CFR 20; l C. Calculate dose commitments to individuals; and i D. I Project doses for the next month due to liquid radioactive effluents.  !

I 1.0 MONITOR ALARM SETPOINT DETERMINATION -

f Monitor alarm setpoints are determined to assure compliance with Tech Specs. The setpoints indicate if the concentration of radionuclides in the liquid effluent at the site boundary exceeds the concentrations specified in 10 CFR 20, Appendix B, to Section 20.1 - 20.601) Table 11, Column 20) for rad (ionuclides other than dissolvej entrained noble gases. The setpoints will also assure that a concentration of 2 x 104 Ci/mi for dissolved or entrained noble gases is not exceeded.  :

i I

Monitor alarm setpoints are calculated monthly. The calculation is performed by the LlODOS computer program. The calculation is based on radionuclides detected in effluent from the release point during the previous month in the following manner:

_ l A. If there were no detectable radionuclides during the previous month, the BWR GALE Code source terms (Table 2.1-1)(2) will be used as the basis for the monthly -l l release rate.

B.

If the calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new tower value.

C.

If the calculated setpoint is greater than the existing monitor setpoint, the setpoint may remain at the lower value or be increased to the new value.

1.1 Radwaste Discharae Line Monitor The following method applies to liquid releases from the plant via the discharge canal when determining the high-high alarm setpoint for the Liquid Radwaste Effluent Monitor during all operational conditions. The radwaste discharge flowrate is assumed to be maintained relatively constant at or near the maximum design flowrate.

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 total 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.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 3 of 15 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.

l l

As I Si . . 2.1 -1 l 3 .

i where Ai . The radioactivity of radionuclide iin the liquid effluent from Table 2.1.1.

1.1.2 Determine Ct, the maximum acceptable total radioactivit of all radionuclides in the liquid effluent prior to dilution (y concentration Ci/ml).

1 Ct F

=

2.1 -2 S:

Ij MPCi where F =

Dilution water flowrate (GPM):

= 240,000 GPM from two circulating water pumps; f = The maximum acceptable discharge flowrate prior to dilution (GPM);

= 50 GPM from the Uquid Radwaste Pump 9);

and MPCi = The liquid effluent radioactivity concentration limit for radionuclide I ( Ci/ml) from Table 5.1.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 4 of 15 i

1.1.3 Determine Cm, the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium) in the liquid discharge prior to l dilution ( Ci/ml).

Cm . Ct - (C tSs) 2.1 -3 1

where Sg = The fraction of the total radioactivity in the liquid effluent comprised of tritium and other radionuclides that do not emit gamma or x ray radiation.

1.1.4 Determine C.R., the calculated monitor count rate above background ,

attributed to the radionuclides (ncps ). l l

Cm C.R. * '

E where E = The detection efficiency of the monitor ( Ci/CC/ CPS) from Plant Chemistry Surveillance procedures.

1.1.5 The monitor high-high alarm setpoint above background (neps) should be set at the C.R. value. Since only one tank can be released at a time,  ;

adjustment of this value is not necessary to compensate for releases from more than one source.

1.2 Discharge Canal Monitor The following method determines the high-high alarm setpoint for the Discharge Canal Monitor during all operational conditions.

1.2.1 Determine the " mix" (radionuclides and composition) of all liquids released into the discharge canal.

A. Determine the liquid source terms that are representative of the

" mix" of allliquid released into discharge canal. Liquid source terms are the total curies of each isotope released during the

]revious month. Table 2.1-1 source terms may be used if there lave been no liquid releases.

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MQNTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 5 of 15 B. Determine Si (the fraction of the total radioactivity of all liquids released into the discharge canal comprised by radionuclide i) for each individual radionuclide released into the discharge canal.

l l

A; Si . 2.1-5 3

where A; , The radioactivity of radionuclide i released into the discharge canal.

1.2.2 Determine Ce, the maximum acceptable total radioactivity concentration of all radionuclides released into the discharge canal ( Ci/ml).

Ce , 1 2.1 -6 Si I

i MPC, )

where )

MPCi = The liquid effluent radioactivity concentration limit for radionuclide i ( Ci/mi) from Table 2.1.1.

1.2.3 Determine Cm the maximum acceptable total radioactivity concentration j of the radionuclides (minus tritium) released into the discharge canal

( Ci/mi).

Cm . Ce - (CoSg) 2.1 -7 l l

where SH = The fraction of the total radioactivity released into the discharge canal comprised of tritium and other radionuclides that do not emit gamma or x-ray radiation.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 6 of 15 31 1.2.4 Determine C.R., the calculated monitor count rate above background attributed to the radionuclides (ncps).

Cm C.R. * .1-8 E

where E = The detection efficiency of the monitor ( Ci/CC/ CPS) from Plant Chemistry Surveillance procedures.

l 1.2.5 The monitor high-high alarm setpoint above background (ncps) should be set at the C.R. value.

1.3 Service Water Discharge Pipe Monitor The following method determines the high-high alarm set-point for the Service Water Discharge Pipe Monitor during all operational conditions.

1.3.1 Determine the " mix" (radionuclides and composition) of the service water effluent.

A. Determine the liquid source terms that are representative 6f the

" mix" of the service water effluent. Liquid source terms are the total curies of each isotope released during the previous month.

, Table 2.1-1 source terms may be used if there have been no l

liquid releases.

B. Determine Si the fraction of the total radioactivity in the service I water effluent comprised by radionuclide i, for each individual radionuclide in the liquid effluent.

I A;

Si , 2.1 -9 yAi i

l where l

A; = The radioactivity of radionuclide iin the service water effluent.

l l

l l

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 l Page 7 of le 1.3.2 Determine Ct, (the maximum acceptable total radioactivity concentration of all radionuclides in the service water effluent prior to ti;!ution

( Ci/ml)). ,

Ct ~

F fy Si 2.1-10 i MPC i where F =

Dilution water flowrate (GPM);

=

240,000 GPM from two circulating water pumps; i f =

The maximum acceptable discharge flowrate prior to dilution (GPM);

10,000 GPM; and MPCi

The liquid effluent radioactivity concentration limit for raolonuclide i ( Ci/ml) from Table 2.1-1.

1.3.3 Determine Cm, (the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium)) in the service water prior to dilution ( Ci/ml).

Cm = Ct - (CtSH) 2.1-10 where Ss = The fraction of the total radioactivity in the service water effluent comprised of tritium and other radionuclides that do not emit gamma or x-ray radiation.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 8 of 15

).

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

Cm C.R. = ^ ~

E where E = The detection efficiency of the monitor ( Ci/CC/ CPS) from l Plant Chemistry Surveillance procedures.  !

1 1.3.5 The monitor high-high alarm setpoint above background (ncps) should be set at the C.R. value.

i 1.4 Turbine Building Normal Drain Sump Monitor j The following method determines the high-high alarm set-point for the Turbine Building Normal Drain Sump Monitor during all operational conditions.

1.4.1 Determine the " mix" (radionuclides and composition) of the TBNDS effluent. -

1 A. Determine the liquid source terms that are representative of the

" mix" of the TBNDS effluent. Uquid source terms are the total 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. l Determine Si, the fraction of the total radioactivity in the TBNDS effluent comprised by radionuclide i, for each individual '

radionuclide in the liquid effluent. i

, I A

Si " 2.1-13 IAi i

where  !

l A; = The radioactivity of radionuclide i in the TBNDS effluent.

l l

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 9 of 15 1.4.2 Determine Ct (the maximum acceptable total radioactivity concentration of all radionuclides in the TBNDS effluent prior to dilution ( Ci/ml)).

i 1

=

f S 3.1-14 i MPCi where I

F = Dilution water flowrate (GPM); l

= 240,000 GPM from two circulating water pumps; I f = The maximum acceptable TBNDS discharge flowrate prior l to dilution (GPM);

l l

= 128 GPM from TBNDS pump 52A.  !

= 110 GPM from TBNDS pump 528.  ;

1 MPCi = The liquid effluent radioactivity concentration lirnit for radion'iclide i( Ci/ml) from Table 2.1-1, 1.4.3 Determine Cm (the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium) in the TBNDS prior to dilution ( Ci/ml).

Cm = Ct - (C tSs) 2.1-10 where  !

Ss = The fraction of the total radioactivity in the TBNDS effluent l comprised of tritium and other radionuclides that do not emit '

gamma or x-ray radiation.

4 l

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1 MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 10 of 15 .

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

Cm C.R. = '

E where E = The detection efficiency of the monitor ( Ci/CC/ CPS) from Plant Chemistry Surveillance procedures.

1.4.5 The monitor high-high alarm setpoint above background (ncps) should be set at the C.R. value.

1.5 Multiple Release Points The discharge canal monitor, service water discharge and TBNDS line monitor are provided to detect unplanned or accidental releases. All normal releases are monitored by the radwaste discharge line monitor. There are, therefore, no multiple release points and monitor settings do not have to be reduced to account for multiple releases. -

2.0 LIQUID EFFLUENT CONCENTRATION - COMPLIANCE WITH TECH SPECS (TS) in order to show compliance with Tech Specs the concentrations of radionuclides in

, liquid effluents are determined and compared with the maximum permissible concentrations (MPC) as defined in Appendix B, to section 20.1 - 20.601, Table 11 of 10CFR 20. The concentration of radioactivity in effluents arior to dilution is determined.

The concentration in diluted effluent is calculated by the L QDOS computer program in conjunction with Surveillance Test Numbers 0377,0238,0239,0240 and 0242, using '

j these results before each batch release, and following each batch release. l l

1 1

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MONTICELLO NUCLEAR GENERATING PLANT ' ODCM-02.01

TITLE: LIQUID EFFLUENTS Revision 1 i Page 11 of 15 i 1

2.1 1 Batch Releases  !

2.1.1 Prerelease The radioactivity content of each batch release is determined prior to release. manner:

following MNGP will show compliance with Tech Specs (TS), in the

! The concentration of the various radionuclides in the batch release prior to dilutionis flow calculation shown toinobtain the concentration the following equation: at the unrestricted area. T Conci = C; R _

2.2-1 MDF .

l where l

,j

' Conci = i concentration of radionuclide i at the unrestricted area,( Ci/mi); i Ci =

concentration of radionuclide iin the potential batch 1 release,( Ci/ml); ,

l R =

release rate of the batch, (GPM);  !

MDF =

minimum dilution flow, (GPM).

The projected concentration in the unrestricted area is com aared to the concentrations in Appendix B, (to Section 20.1 - 20.601) Ta]Ie 11 of 10CFR 20. These concentrations are given in Tabie 5.1. Before a release may occur, Equation 2.2-2 must be met for all nuclides. For the MNGP the MDF is 240,000 GPM. The maximum release rate is 50 GPM.

I Conci <1 4.2-2 i MPCi where MPCi =

maximum concentration of radionuclide i from Reference 2, ( Ci/ml).

3.0 LIQUID EFFLUENT DOSES - COMPLIANCE WITH 10 CFR 50 Doses resulting from liquid effluents are calculated monthly to show compliance with 10 CFR 50. These calculations are performed by the LIODOS computer program in conjunction with Surveillance Test 0374. A cumulative summation of total body and organ doses for each calendar quarter and calendar year is maintained as well as projected doses for the next month.

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MONTICELLO NUCLEAR GENERATING PLANT ' ODCM-02.01 i TITLE: LIQUID EFFLUENTS Revision 1 Page 12 cf 15 4 3

! )

3.1 Determination of Liquid Effluent Dilution  !

To determine doses from liquid effluents the near field average dilution factor for the period of release must be calculated. This dilution factor must be calculated for each batch release. The dilution factor is determined by:

Rx  ;

F=

k #

X ADFk

)

1 where  !

Rk = release rate of the batch during time period k, (GPM);  ;

and j ADFx= actual dilution flow during the time period of release k, (GPM).

The value of X is the site specific value for the mixing effect of the MNGP  !

discharge structure. This value is 1.0 for MNGP while operating in the once-through cooling mode. Although not expected to occur, if radioactive material is discharged while operating in the recycle mode, this value may be i 1.86. W  !

l 3.2 Dose Calculations The dose contribution from the release of liquid effluents is calculated monthly.

The dose contribution is calculated using the following equation:

Dj = IIA;jt C Fk ik k 4.3-2 ki where Dj = the dose commitment to the total body or any organ, from the liquid effluents for the 31 day period, (mrem);

Cg i

= the average concentration of radionuclide, i, in undiluted liquid effluent for release k, ( Ci/ml);

Aji = the site related ingestion dose commitment factor to the total body or any organ j for each identified principal gamma and beta emitter, (mrem /hr per Ci/mi);

Fk = the near field average dilution factor for Cik during liquid effluent release k, as defined in Equation 4.3-1, and tg = the length of time for release k, (hours).

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i ,MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 13 of 15 The dose factor Aji was calculated for an adult for each isotope using the following equation:

=

Aq 1.14 x 105 (730/Dw + 21BF) i DFj i 2.3-3 where '

1.14 x 105 = jos oCi 103ml 1 vr Ci liter 8760 hr l

730 = adult water consumption rate, (liters /yr);

Dw = dilution factor from the near field area to the potable water intake for adult water consumption; l

21 = adult fish consumption, (kg/yr);  !

BFi =

bicaccumulation factor for radionuclide i in fish from Table A-1 of l Regulatory Guide 1.109 Rev.1, (5) (pCi/Kg per pCi/ liter);

DFji = dose conversion factor for radionuclide i for adults for particular organ j from Table E-11 of Regulatory Guide 1.109 Rev.1, (mrem /pCi).

The Aq values for an adult at the MNGP are given in Table 4.2. The far field dilution factor, Dw for the MNGP is 7:1 for the nearest downstream water supply in St. Paul. This value was determined by assuming that effluents are

• completely mixed in 50% of the Mississippi River flow (7431 cfs at Anoka, MN).

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 14 of 15

, 3 3.3 )

Cumulation of Doses Doses calculated monthly are summed for comparison with quarterly and annual limits. The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest. This summation is performed by the LIODOS computer program.

For the quarter, D s 1.5 mrem total body 2.3-4 D s 5 mrem any organ 2.3-5 For the Calendar Year, D s 3 mrem total body 2.3-6 D s 10 mrem any organ 2/3-7 The quarterly limits given above represent one half of the annual design objective.(7) If these quarterly or annual limits are exceeded, a special report should be submitted stating the reason and corrective action to be taken. This ._

report will include results of analyses of Mississippi River water and an analysis of possible impacts through the drinking water pathway. If twice these limits are exceeded, a special report will be submitted showing compliance with 40CFR 190.(a) 3.4 Projection of Doses Anticipated doses resulting from the release of liquid effluents are projected monthly. If the projected doses for the month exceeds two percent of Equation 2.3-6 or 2.3-7, additional components of the liquid radwaste treatment system will be used to process waste. The projected doses are calculated using Equation 2.3-2. This calculation is performed by the LIODOS com in conjunction with Surveillance Test 0375. The dilution factor, k is F , puter program calculated by replacing the term ADFkin Equation 2.3-1 with the term MDF from Equation 2.2-1. i The total source term utilized for the most recent dose calculation should be used for the prolections unless information exists indicating that actual releases could differ sign ficantly in the next month. In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming l month.

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-02.01 TITLE: LIQUID EFFLUENTS Revision 1 Page 15 of 15 REFERENCES 1.

USNRC, Title 10, Code of Federal Regulation, Part 20, " Standards for Protection Against Radiation", Appendix B, Table 11, Column 2.

2.

NSP - Monticello Nuclear Generating Plant, Appendix I Analysis - Supplement No.

1 - Docket No. 50-263, Table 2.1-2.

3.

NSP - Monticello Nuclear Generating Plant, Appendix I Analysis - Supplement No.

1 - Docket No. 50-263, Table 2.1-1. '

4. Boegli, J.S., et. al. Eds, Section 4.3 in " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133,1978, NTIS, Springfield Va.

5. USNRC, Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance l with 10 CFR 50, Appendix I", Rev.1, Oct.1977, USNRC, Washington D.C.

{

6.

NSP - Monticello Nuclear Generating Plant, Final Draft Safety Analysis Report -

Amendment 4, Question 3.3, and Amendment 8 in entirety.

7.

USNRC, Title 10, Code of Federal Regulation, Part 50, " Domestic Licensing of Production and Utilization Facilities", Appendix 1, " Numerical Guides for Design Objectives and Umiting' Conditions for Operation to Meet the Criterion As Ldw as is Reasonably Achievable for Radioactive Materialin Ught-Water-Cooled Nuclear Power Reactor Effluents"

8. EPA, Title 40, Code of Federal Regulations, Part 190 " Environmental Radiation Protection Standards for Nuclear Power Operations" ,

1 I

1 l

1 l

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-OS.01 TITLE: RADIATION ENVIRONMENTAL Revision 1 MONITORING PROGRAM Page 1 of 2 i

l Prepared By: Ch)p Reviewed By:

(([ _

OC Final Review Meeting:

M g/fK Date: /6-[fo/pg Approved By:

h L/

c/y/99 ll l1 L*1i@F3@$fMSDFJQ$isif4Di?EORWDMINISTRATIVE;USE'ONIXiG$lFgf)??il?iff9E5@RFl y EMS 5 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: 7,7- c5 % 92 -17LL Resp Supv I1 CHEM l Assoc Ref- CHEM i ARMS: ODCM-05.01 l Doc Type: 7030 (lS8: N Freq: 2) yrt, .

l Admin Initials: \ #@ Date:J/lf)/U (

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-05.01 TITLE: RADIATION ENVIRONMENTAL Revision 1 MONITORING PROGRAM Page 2 of 2 l 1.0 SAMPLING Table 5.1-1 and Figure 5.1-1 specify the current sampling locations for the radiation environmental monitoring program. These sampling locations are based on the latest land use census.

If it is learned from an annual census that milk animals or gardens are present at the location which yields a calculated thyroid dose greater than those locations previously sampled, the new milk animal or garden locations resulting in the higher calculated doses SHALL be added to the surveillance program as soon as practicable. Sample locations (except the control) having lower calculated doses may be dropped from the program at the end of the grazing or growing season (October 31) to keep the total number of sample locations constant.

If the plant begins routine discharges oiliquid radioactive effluent into the Mississippi River, a land use survey will be conducted to determine whether any crops are irrigat with water taken from the Mississippi River between the plant discharge canal and a point 5 miles downstream. If edible crops are being irrigated from Mississippi River water, appropriate samples will be collected and analyzed per Technical Specifications Table 4.16.1.

2.0 INTERLABORATORY COMPARISON PROGRAM Analyses SHALL be performed on radioactive materials supplied as part of an NRC approved interlaboratory comparison program. This program involves the analyses of ,

I samples provided by a control laboratory and comparison of results with those of the f control laboratcry as well as with other laboratories which receive portions of the same I samples. Media used in this program (air, milk, water, etc.) SHALL be limited to those found in the radiation environmental monitoring program. The results of analyses performed as a part of the crosscheck program SHALL be included in the Annual ,

Radiation Environmental Monitoring Report.

l 3.0 BASES l

Section 1.0, paragraph 3, is worded to conform to LAR-39 and its associated NRC '

Safety Evaluation (SER).

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s MONTICELLO NUCLEAR GENERATING PLANT ODCM-13.05 TITLE: ODCM-05.01 TABLES Revision 2 Page 1 of 5 Prepared By:

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> . . ; l MONTICELLO NUCLEAR GENERATING PLANT ODCM-13.05 TITLE: ODCM-05.01 TABLES Revision 2 Page 2 of 5

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Table 5.1-1 Monticello Nuclear Generating Plant Radiation Environmental Monitoring Program Sampling Locations Location Distance Compass Type of Sample Code Collection Site Miles Heading Sector River water M-8c Upstream of plant w/in 1000 ft upstream of plant intake w/in 1000 ft downstream of plant River water M-9 Downstream of plant discharge Drinking water M-14 City of Minneapolis 36. 128 SE Well water M-10c Goenner Farm 12.5 321 NW Well water M-11 City of Monticello 3.2 128 SE Well water M-12 Plant Well No.1 0.2 267 W Well water M-27 Wise Residence 0.7 200 SSW l

Sediment-River M-8c Upstream of plant w/in 1000 ft upstream of plant intake w/in 1000 ft downstream of plant i Sediment-River M-9 Downstream of plant discharge Sediment-Shoreline M-15 Montissippi Park 1.6 11 7 ESE Periphyton or Upstream of plant w/in 1000 ft upstream of plant intake  !

Macroinver-tebrates M-8e w/in 1000 ft downstream of plant M-9 Downstream of plant discharge Fish i M-8c Upstream of plant w/in 1000 ft upstream of plant intake w/in 1000 ft downstream of plant I Fish M-9 Downstream of plant discharge l Milk M-10c Goenner Farm 12.5 321 NW Milk M-24 Weinand Farm 4.8 180 S Milk M-28 Hoglund Farm 3,7 300 WNW 1/mab

s, MONTICELLO NUCLEAR GENERATING PLANT ODCM-13.05 TITLE: ODCM-05.01 TABLES Revision 2 Page 3 of 5 Table 5.1-1 Monticello Nuclear Generating Plant Radiation Environmental Monitoring Program Sampling Locations (Cont'd) 1 Location Distance Compass Type of Sample Code Collection Site Miles Heading Sector Cultivated crops (leafy green vegetables)

M-10c a. Available Producer > 10.0 a. a.

M-27 Highest D/O Garden 0.7 200 SSW (corn)*

(potatoes)*

Particulates and Radicio-  !

dine I (air) M-1 c Air Station M-1 11.1 306 NW (air) M-2 Air Station M-2 0.8 140 SE (air) M-3 Air Station M-3 0.6 104 ESE (air) M-4 Air Station M-4 0.9 150 SSE (air) M-5 Air Station M-5 2.7 136 SE Direct Radiation - (general area of the site boundary)

(TLD) M01A North Boundary Rd. 0.7 353 N (TLD) M02A North Boundary Rd. 0.8 23 NNE (TLD) M03A North Boundary Rd. 0.1 43 NE (TLD) M04A Biology Station Rd. 0.7 92 E l (TLD) MO5A Biology Station Rd. 0.6 112 ESE (TLD) M06A Biology Station Rd. 0.6 133 SE (TLD) M07A County Road 75 0.5 158 SSE I (TLD) M08A County Road '75 0.5 183 S (TLD) M09A County Road 75 0.4 203 SSW (TLD) M10A County Road 75 0.3 225 SW (TLD) M11A County Road 75 0.4 250 WSW Collected only if plant discharges radioactive offluent into the river, then only from river irrigated fields. (See Sec. 5.1)

(TLD) M12A County Road 75 0.7 273 W

' (TLD) M13A North Boundary Rd. 1.1 317 NW I/mab m- -

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MONTICELLO NUCLEAR GENERATING PLANT ODCM-13.05 TITLE: ODCM-05.01 TABLES Revision 2 Page 4 of 5 Table 5.1-1 Monticello Nuclear Generating Plant Radiation Environmental Monitoring Program Sampling Locations (Cont'd)

Location i Distance Compass Type of Sample Code Collection Site Miles Heading Sector j (TLD) M14A North Boudnary Rd. 0.8 338 NNW l Direct Radiation - (about 4 to 5 miles distant from the plant)

(TLD) M01B Sherco No.1 Air Sta. 4.6 2 N (TLD) M02B County Road 11 4.4 17 NNE (TLD) M03B County Rd. 73 & 81 4.5 49 NE (TLD) M04B Sherco No. 6 Air Sta. 4.2 67 ENE (TLD) M058 City of Big Lake 4.4 87 E ,

(FLD) M068 County Rd 14 & 196 4.3 116 ESE )

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(TLD) M07B Monte Industrial Dr. 4.4 135 SE 1 (TLD) M088 Dale Larson Res. 4.6 162 SSE (TLD) M09B Norbert Weinand 4.7 180 S ..

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Farm 1 (TLD) M10B John Reisewitz Farm 4.4 206 SSW' (TLD) M118 Clifford Vanlith Farm 4.2 225 SW )

, (TLD) M12B Lake Maria St. Park 4.4 253 WSW l (TLD) M13B Bridgewater Sta. 4.1 271 W l (TLD) M148 Richard Anderson 4.5 288 WNW Res. '

(TLD) M15B Gary Williamson Res. 4.5 308 NW (TLD) M16B Sand Plain Research 4.3 338 NNW j Farm Direct Radiation - (special interest locations)

(TLD) M01S Osowski Farm Market 0.7 130 SW (TLD) M02S Edgar Klucas Res. 0.7 142 SE (TLD) M03S Big Oaks Park 1.3 89 E  !

(TLD) M04S Pinewood School 2.3 132 SE (TLD) MOSS Rivercrest Christian 2.6 112 ESE Academy (TLD) M06S Monte Public Works 2.7 136 SE (TLD) M01C Krchenbauer Farm 11.5 323 NW l/mab t

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s. MONTICELLO NUCLEAR GENERATING PLANT ODCM-13.05 TITLE: ODCM-05.01 TABLES Revision 2 -

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l Notes on Table 5.1-1:

l "c" denotes control locations. All other locations are indicator locations.

a. Control " leafy green" vegetable will be taken in locations as available outside 10 mi.

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The letters after TLD code numbers have the following meanings:

A Locations in the general area of the site boundary;  ;

8 Locations about 4 to 5 miles distant from the plant; l S Specialinterest locations.

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