ML20132A202

Annual Radioactive Effluent Release Report Including Off-site Dose Calculation Manual Changes

ML20132A202
Person / Time
Site:	Cook
Issue date:	04/29/2020
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20132A208	List: AEP-NRC-2020-35, Submittal of 2019 Annual Radioactive Effluent Release Report ML20132A202
References
AEP-NRC-2020-35
Download: ML20132A202 (106)

Text

OFF-SITE DOSE CALCULATION MANUAL CHANGES The Off-Site Dose Calculation Manual, PMP-6010-0SD-001, was revised during this 2019 reporting period. The new revision (#26) was a major revision supporting the Radiation Monitor Replacement projects, and went into effect on April 24, 2019.

This revision is a transition document covering both the older monitors and the new replacements. It is anticipated that a new revision will occur in 2020 with the completion of the project to clear out the old equipment references. Revision 26 has been attached.

A3.0-1

Doc No.:

Title:

Alteration Cat.:

CDl/50.59:1 CDl/50.59:2 PORC Mtg. No.:

GARB Mtg. No.:

Admin Hold AR No.:

Superceding Proc(s):

Temp Proc Exp Date:

Temp Change Exp Date:

Temp Proc/Change End:

Effective Date:

!Name Hershberger, Robert (i396199)

Smith, Larry D (i830114)

Gressley, Scott (i344612)

Simpson, Kevin (s222639)

Raye, David (i728074)

Abbgy, Bruce (i001155)

PMP-6010-0SD-001

• OFF-SITE DOSE CALCULATION MANUAL Major Revision - Full Review EC-0000053363 EC-0000053364 4785 N/A 4/24/2019 12:00:00 AM Approvals

!!Review/Approval Type/Capacity 11Date Rev 026 No.:

11 Cross-Discipline Review: CHEMISTRY 1104/13/2019 09:47 1 Cross-Discipline Review :

1104/13/2019 22:15 MAINTENANCE - l&C 11 Cross-Discipline Review: OPERATIONSII04/14/2019 00:53 1 Cross-Discipline Review: EMERGENCYll0411412019 09.31 PREPAREDNESS 1 Cross-Discipline Review: RADIATION 1104/16/2019 18:10 PROTECTION 13 Technical Review 1104/19/2019 07:53 McCarthy, Michael K I (s243583)

5 Management Review 1104/19/2019 16:14 Ferneau, Kelly J 17 Approval Authority 1104/20/2019 01 :23 (s252555)

Signature Comments The only thing I found was step3.3.1.a.5 has "Error! Reference source not found., Error!

Reference source not found."

Page 33, Step 3.3.2 b.1, should read vent stack noble gas channels to consistent with step 3.3.2 c.1 on page 34. Ensure the Att. 3.23 Map copies correctly

!Comments provided to the procedure writer.

I

I INDIANA PMP-6010-0SD-001 Rev. 26 Page 1 of 98 MICHIGAN 1 PO~R OFF-SITE DOSE CALCULATION MANUAL Information I

Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization TABLE OF CONTENTS 1

PURPOSE AND SCOPE............................................................................. 4 2

DEFINITIONS AND ABBREVIATIONS........................................................ 4 3

DETAILS................................................................................................ 6 3.1 Calculation of Off-Site Doses............................................................... 6 3.1.1 Gaseous Effluent Releases........................................................ 6 3.1.2 Liquid Effluent Releases......................................................... 12 3.2 Limits of Operation and Surveillances of the Effluent Release Points............. 15 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation................ 15 3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation.............. 16 3.2.3 Liquid Effluents.................................................................... 17

a. Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge.............................................................. 17

b. Concentration of Releases from the TRS Discharge.................... 18

c. Dose............................................................................ 19

d. Liquid Radwaste Treatment System....................................... 19 3.2.4 Gaseous Effluents.................................................................. 22

a. Dose Rate...................................................................... 22

b. Dose - Noble Gases.......................................................... 22

c. Dose - Iodine-131, Iodine-13 3, Tritium, and Radioactive Material in Particulate Form........................................................... 23

d. Gaseous Radwaste Treatment............................................... 23 3.2.5 Radioactive Effluents - Total Dose................................................ 26 3.3 Calculation of Alarm/Trip Setpoints...................................................... 27 3.3.1 Liquid.Monitors.................................................................... 28

a. Liquid Batch Monitor Setpoint Methodology............................ 28

b. Liquid Continuous Monitor Setpoint Methodology..................... 29 3.3.2 Gaseous Monitors.................................................................. 31

a. Plant Unit Vent............................................................... 32

b. Waste Gas Storage Tanks................................................... 35

c. Containment Purge and Exhaust System.................................. 35

d. Steam Jet Air Ejector System (SJAE)..................................... 36

e. Gland Seal Condenser Exhaust............................................. 3 7

I INDIANA PMP-6010-0SD-001 Rev. 26 Page 2 of 98 MICHIGAN l POw_ER OFF-SITE DOSE CALCULATION MANUAL Information I

Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization 3.4 Radioactive Effluents Total Dose.......................................................... 37 3.5 Radiological Environmental Monitoring Program (REMP)................ :........ 37 3.5.1 Purpose of the REMP............................................................. 37 3.5.2 Conduct of the REMP............................................................ 38 3.5.3 Annual Land Use Census........................................................ 41 3.5.4 Interlaboratory Comparison Program........................................ 41 3.6 Meteorological Model......................................................................... 42

3. 7 Reporting Requirements..................................................................... 42 3.7.1 Annual Radiological Environmental Operating Report (AREOR)..... 42

3. 7.2 Annual Radiological Effluent Release Report (ARERR).................. 43 3.8 10 CFR 50. 75 (g) Implementation........................................................ 45 3.9 Reporting/Management Review............................................................ 46 4

FINAL CONDITIONS............................................................................... 46 5

REFERENCES........................................................................................ 46 SUPPLEMENTS.1 Dose Factors for Various Pathways.............................................. Pages 50 - 53.2 Radioactive Liquid Effluent Monitoring Instruments................... Pages 54 - 56.3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements............................................................ Pages 57 - 58.4 Radioactive Gaseous Effluent Monitoring Instrumentation.......... Pages 59 - 62.5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements............................................................ Pages 63 - 65.6 Radioactive Liquid Waste Sampling and Analysis Program........ Pages 66 - 67.7 Radioactive Gaseous Waste Sampling and Analysis Program..... Pages 68 - 69.8 Multiple Release Point Factors for Release Points......................... Page 70 - 71

I INDIANA MICHIGAN PMP-6010-0SD-001 Rev. 26 Page 3 of 98 PO~ER OFF-SITE DOSE CALCULATION MANUAL Information I

Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization.9 Liquid Effluent Release Systems........................................................... Page 72.10 Plant Liquid Effluent Parameters........................................................... Page 73.11 Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline and Mirion Liquid Monitors.......................................................................................... Page 74 - 75.12 Counting Efficiency for R-19, 1/2-DRA-300, R-24, and l/2-DRA-353................................................................................. Pages 76 - 79.13 Counting Efficiency for R-20, R-28, 1-WRA-713, 2-WRA-714, l-WRA-717, and 2-WRA-718.................................................. Page 80-82.14 Gaseous Effluent Release Systems........................................................ Page 83.15 Plant Gaseous Effluent Parameters........................................................ Page 84.16 10 Year Average of 1995-2004 Data............................................ Pages 85 - 86.17 Annual Evaluation of x/Q and D/Q Values For All Sectors................. Page 87.18 Dose Factors.................................................................................. Pages 88 - 89.19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies............................... Pages 90 - 93.20 Maximum Values for Lower Limits of Detections A,B _ REMP.... Pages 94 - 95.21 Reporting Levels for Radioactivity Concentrations in Environmental Samples.......................................................................... Page 96.22 On-Site Monitoring Location - REMP................................................... Page 97.23 Off-Site Monitoring Locations - REMP................................................. Page 98

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PURPOSE AND SCOPE NOTE:

The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the Radioactive Effluent Controls Program (RECP), contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as defined in NUREG-0472, and fully implements the requirements of Technical Specification 5.5.3, Radioactive Effluent Controls Program.

The ODCM contains the methodologies and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.

The ODCM provides flow diagrams detailing the treatment path and the major components of the radioactive liquid and gaseous waste management systems.

The ODCM presents maps of the sample locations and the meteorological model used to estimate the atmospheric dispersion and deposition parameters.

The ODCM specifically addresses the design characteristics of the Donald C. Cook Nuclear Plant based on the flow diagrams contained on the "OP Drawings" and plant "System Description" documents.

Revision 26 of this document covers a transition of Radiation Monitoring System (RMS) equipment. Sections and attachments will have guidance for both the currently installed equipment and the pending Mirion replacement equipment, so users will need to verify the plant equipment status and select the appropriate guidance for that particular installed equipment. Mirion guidance will have the Mirion name or equipment ID attached.

2 DEFINITIONS AND ABBREVIATIONS Term:

Meaning:

Sor shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Dor daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W or weekly At least once per 7 days Mor monthly At least once per 31 days Q or quarterly At least once per 92 days SA or semi-annually At least once per 184 days R

At least once per 549 days.

S/U Prior to each reactor startup p

Completed prior to each release B

At least once per 24 months Sampling evolution Process of changing filters or obtaining grab samples

I_

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Venting All persons who are not occupationally associated with the plant. Does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

The controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

The qualitative assessment of Channel response when the Channel sensor is exposed to a radioactive source.

Total Fractional Level is defined as:

TFL = CoJ + Cr2J +... ~ l Lr1J L(2)

Where:

C(l)

=

Concentration of 1st detected nuclide C<2>

=

Concentration of 2nd detected nuclide L<l)

=

Reporting Level of 1st nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

L<2>

=

Reporting Level of 2nd nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

Controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required.

Vent, used in system names, does not imply a venting process.

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DETAILS 3.1 Calculation of Off-Site Doses 3.1.1 Gaseous Effluent Releases

a.

The computer program MIDAS (Meteorological Information and Dose Assessment System) performs the calculation of doses from effluent releases. The site-specific parameters associated with MIDAS reside in the following subprograms:

MIDER MIDEX MIDEL MIDEG MIDEN

b.

The subprogram used to enter and edit gaseous release data is called MDlEQ (EQ). The data entered in EQ can be used to calculate the accumulation of dose to individual land based receptors based on hourly meteorology and release data. The air dose from this data is calculated via the XDAIR subprogram in MIDAS. It computes air dose results for use in Reg. Guide 1.21 reports and 10 CFR 50 Appendix I calculations based on routine releases.

c.

The formula used for the calculation of the air dose is generated from site specific parameters and Reg. Guide 1.109 (Eq 7):

Where:

Dr, Dp air=~ *'f.[(M;or N;) *Q;

• 3.17E-8]

Dy, D~ air = the gamma or beta air dose in mrad/yr to an individual receptor x I Q

= the annual average or real time atmospheric dispersion factor over land, sec/m3 from.16, IO Year Average of 1995-2004 Data Mi

= the gamma air dose factor, mrad m3 / yr µCi, from Attachment 3.18, Dose Factors Ni

= the beta air dose factor, mrad m3 / yr µCi, from.18, Dose Factors

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= the release rate of radionuclide, "i", in µCi/yr.

Quantities are determined utilizing typical concentration times volumes equations that are documented in 12-THP-6010-RPP-601, Preparation of the Annual Radioactive Effluent Release Report.

= number of years in a second (years/second).

d.

The value for the ground average x IQ for each sector is calculated using equations shown below. Formula used for the calculation is generated from parameters contained in MIDAS Technical Manual, XDCALC (Eq 2).

Where:

~

2.03 x,Q=_ *

• T1 Umg X Lg 2

Lg= minimumof cl +He or Lg=.Jj a-

-g 2tr

-g x = distance downwind of the source, meters. This information is found in parameter 5 of MID EX.

Umg = wind speed for ground release, (meters/second) er =c = vertical dispersion coefficient for ground release, (meters),

(Reg. Guide 1.111 Fig.l)

He = building height (meters) from parameter 28 of MIDER.

(Containment Building = 49.4 meters)

Tf = terrain factor ( = 1 for Cook Nuclear Plant) because we consider all our releases to be ground level (see parameter 5 in MIDEX).

2.03 = -J 2 + 1r + 0.393 radians (22.5°)

e.

The dose due to gaseous releases, other than the air dose, is calculated by the MIDAS subprogram GASPRO. GASPRO computes the accumulation of dose to individual receptors based on hourly meteorology and release data. Calculations consider the effect of each important radionuclide for each pathway, organ, age group, distance and direction.

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f.

Calculations are based on the environmental pathways-to-man models in Reg. Guide 1.109. The program considers 7 pathways, 8 organs, and 4 age groups in 16 direction sectors. The distances used are taken from the MIDEG file.

g.

The formulas used for the following calculations are generated from site specific parameters and Reg. Guide 1.109:

1.

Total Body Plume Pathway (Eq 10)

Dose(mrem/year)=3.17E-8*'f..(Q *,iiQ* S1

• DFB)

Where:

Sr = shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy (maximum exposed individual = 0.7 per Table E-15 of Reg. Guide 1.109)

DFBi = the whole body dose factor from Table B-1 of Reg.

Guide 1.109, mrem - m3 per µCi - yr. See Attachment 3.18, Dose Factors.

Qi = the release rate of radionuclide "i", in µCi/yr

2.

Skin Plume Pathway (Eq 11)

Dose (mrem/yr) =3.l7E-8* s1 * ~ * [z.(Q; *I.II* DFr )+ z.(Q;

• DFS;)]

Where:

1.11 = conversion factor, tissue to air, mrem/mrad DF ir the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", in mrad m3 / µCi yr from Table B-1, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.

DFSi = the beta skin dose factor for a semi-infinite cloud of radionuclide "i", in mrem m3/µCi yr from Table B-1, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.

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3.

Radionuclide and Radioactive Particulate Doses (Eq 13 & 14)

The dose, D1P in mrem/yr, to an individual from radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released to unrestricted areas will be determined as follows:

DiP (mrem/year) = 3.17E -8

• L( R;

• W

• Q;)

Where:

Ri = the most restrictive dose factor for each identified radionuclide "i", in m2 mrem sec/ yr µCi (for food and ground pathways) or mrem m 3 / yr µCi (for inhalation pathway), for the appropriate pathway For sectors with existing pathways within five miles of the site, use the values of R; for these real pathways, otherwise use pathways distance of five miles. See Attachment 3.1, Dose Factors for Various Pathways, for the maximum Ri values for the most controlling age group for selected radionuclides. Ri values were generated by computer code PARTS, see NUREG-0133, Appendix D.

W

= the annual average or real time atmospheric dispersion parameters for estimating doses to an individual at the worst case location, and where W is further defined as:

Wm = x IQ for the inhalation pathway, in sec/m3

-OR-W fg D IQ for the food and ground pathways in l/m2 Qic = the release rate of those radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days, in µCi/yr

h.

This calculation is made for each pathway. The maximum computed dose at any receptor for each pathway is selected. These are summed together to get the dose to compare to the limits. Only the maximum of the cow milk or goat milk pathway (not both) is included in the total.

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i.

In addition to the above routines, the QUICKG routine of the MIDAS system may be used to provide data used in the monthly reports due to its ability to use annual average meteorological data rather than real time data, thus shortening the run time involved.

J.

Carbon-14 (C-14) supplemental information

1.

The quantity of C-14 released to the environment may be estimated by use of a C-14 source term scaling factor based on power generation (Ref. RG 1.21, Revision 2). A recent study recommends a source term scaling factor of approximately 9.0 to 9.8 Curies/GWe-yr for a Westinghouse Pressurized Water Reactor (Ref.

EPRI 1021106 "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents" December 23, 2010). For this method, a scaling factor of 9.4 Curies/GWe-yr shall be used.

2.

C-14 releases from PWRs occur primarily as a mix of organic carbon (methane) and inorganic carbon (carbon dioxide). For this method, an average organic fraction of 80 % with the remaining 20 % being assumed as carbon dioxide shall be used.

3.

Dose is calculated utilizing the methodology prescribed in RG 1.109 Appendix C, with the vegetation dose being the most predominant.

Adjustments for growing seasons, percentage of C-14 generated assumed released from the reactor coolant in gaseous form via batch releases, seasonal X I Q, and other industry methodologies being considered by the NRC may be applied as desired should their acceptance of these methods occur.

k.

Steam Generator Blowdown System (Start Up Flash Tank Vent)

1.

The amount of radioiodine and other radionuclides that are released via the startup flash tank and its vent are calculated through actual sample results while the startup flash tank is in service.

2.

The following calculation is performed to determine the amount of curies released through this pathway. (Plant established formula.)

Curies*= µCi *GPM*timeonflashtank(min)* 3. 785E-3 ml Where: 3.785E-3 = conversion factor, ml Ci/µCi gal.

3.

The flow rate is determined from the blowdown valve position and the time on the startup flash tank, or using installed plant blowdown flow instrumentation. Chemistry Department performs the sampling and analysis of the samples.

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4.

This data is provided to the MIDAS computer and dose calculations (liquid and gas) are performed to ensure compliance with Subsection 3.2, Limits of Operation and Surveillances of the Effluent Release Points, dose limits. MIDAS uses the formulas given in step 3.1.2, Liquid Effluent Releases, to calculate doses to members of the public.

This section provides the minimum requirements to be followed at Donald C.

Cook Nuclear Plant. This would be used if actual sample data was not available each time the startup flash tank was in service.

5.

The radioiodine release rate must be determined in accordance with the following equation every 31 day period whenever the specific activity of the secondary coolant system is greater than 0.01 µCi/g dose equivalent 1-131.

6.

IF the specific activity of the secondary coolant system is less than 0.01 µCilg dose equivalent 1-131, THEN the release rate must be determined once every six months. Use the following plant established equation:

Q.v = Ci* !PF*

Rsgb Where:

Qy = the release rate of 1-131 from the steam generator flash tank vent, in µCi/sec Ci the concentration (µCi/cc) of 1-131 in the secondary coolant averaged over a period not exceeding seven days IPF = the iodine partition factor for the Start Up Flash Tank, 0.05, in accordance with NUREG-0017 Rsgb = the steam generator blowdown rate to the startup flash tank, in cc/ sec

7.

Use the calculated release rate in monthly dose projections until the next determination to ensure compliance with Subsection 3.2, Limits of Operation and Surveillances of the Effluent Release Points, dose limits. Report the release rate calculations in the Annual Radioactive Effluent Release Report.

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a.

The calculation of doses from liquid effluent releases is also performed by the MIDAS program. The subprogram used to enter and edit liquid release data is called MDlEB (EB).

b.

To calculate the individual dose (mrem), the program DS1LI (LD) is used. It computes the individual dose for up to 5 receptors for 14 liquid pathways due to release of radioactive liquid effluents. The pathways can be selected using the MIDEL program and changing the values in parameter 1. D.C. Cook Nuclear Plant uses 3 pathways: potable water, shoreline, and aquatic foods (fresh water sport fishing).

c.

Steam Generators are typically sparged, sampled, and drained as batches usually early in outages to facilitate cooldown for entry into the steam generator. This is also typically repeated prior to startup to improve steam generator chemistry for the startup. The sample stream, if being routed to the operating unit blowdown, is classified as a continuous release for quantification purposes to maintain uniformity with this defined pathway.

d.

The equations used are generated from site specific data and Reg. Guide 1.109. They are as follows:

1.

Potable Water (Eq 1)

=1100*

Uap

• "'Q * * * -).;,,

RapJ MP* F

• 2.23E - 3 ~ i Dmpj e Where:

Rapi = the total annual dose to organ "j" to individuals of age groups "a" from all of the nuclides "i" in pathway "p",

in mrem/year 1100 = conversion factor, yr ft3 pCi / Ci sec L Uap = a usage factor that specifies the exposure time or intake rate for an individual of age group "a" associated with pathway "p". Given in #29-84 of parameter 4 in MIDEL and Reg. Guide 1.109 Table E-5. See.1, Dose Factors for Various Pathways.

MP = the dilution factor at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food). Given in parameter 5 of MID EL as 2.6.

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= the circulation water system water flow rate, in gpm, is used for evaluating dose via these pathways as dilution flow 2.23E-3 = conversion factor, ft3 min/ sec gal Qi

= the release rate of nuclide "i" for the time period of the run input via MIDEB, Curies/year.

Daipi = the dose factor, specific to a given age group "a",

radionuclide "i", pathway "p", and organ "j", which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/ pCi. These values are taken from tables E-11 through E-14 of Reg. Guide 1.109 and are located within the MIDAS code.

Ai

= the radioactive decay constant for radionuclide "i", in hours-1 tp

= the average transit time required for nuclides to reach the point of exposure, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This allows for nuclide transport through the water purification plant and the water distribution system. For internal dose, tp is the total elapsed time between release of the nuclides and ingestion of food or water, in hours. Given as #25 of parameter 4 in MID EL. ( tp = 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

2.

Aquatic Foods (Eq 2)

Where:

= 1100*

Uap

• '°'Q * * * * * -).;Ip Rap1 MP* F

• 2.23E -3 ~ ;

B,p Da,p1e Bip = the equilibrium bioaccumulation factor for nuclide "i" in pathway "p", expressed as pCi L / kg pCi. The factors are located within the MIDAS code and are taken from Table A-1 of Reg. Guide 1.109. See Attachment 3.1, Dose Factors for Various Pathways.

tp

= the average transit time required for nuclides to reach the point of exposure, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows for decay during transit through the food chain, as well as during food preparation. Given as #26 of parameter 4 in MID EL.

( tp = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

MP = the dilution factor at the point of exposure, 1.0 for Aquatic Foods. Given in parameter 5 of MID EL as 1.0.

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3.

Shoreline Deposits (Eq 3)

U *W R.=JJOOOO*

ap

• "'Q

• T

• D * -[-J..;tp]*[l- -J.;tb]

ap; Mp*F*2.23E-3 ~ '

atpj e e

Where:

W = the shoreline width factor. Given as an input of 0.3 when running the program, based on Table A-2 in Reg.

Guide 1.109.

Ti

= the radioactive half-life of the nuclide, "i", in days Daipi = the dose factor for standing on contaminated ground, in mrem m2 I hr pCi. The values are taken from table E-6 of Reg. Guide 1.109 and are located within the MIDAS code.

See Attachment 3.1, Dose Factors for Various Pathways.

tb

= the period of time for which sediment or soil is exposed to the contaminated water, 1.31E+5 hours. Given in MID EL as item 6 of parameter 4.

tr

= the average transit time required for nuclides to reach the point of exposure, 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Given as #28 of parameter 4 inMIDEL.

110,000 = conversion factor yr ft3 pCi / Ci sec m2 day, this accounts for proportionality constant in the sediment radioactivity model Mp = the dilution factor at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food). Given in parameter 5 of MID EL as 2.6.

)

e.

The MIDAS program uses the following plant specific parameters, which are entered by the operator.

1.

Irrigation rate = 0

2.

Fraction of time on pasture = 0

3.

Fraction of feed on pasture = 0

4.

Shore width factor= 0.3 (from Reg. Guide 1.109, Table A-2)

f.

The results of DSlLI are printed in LDRPT (LP). These results are used in the monthly report of liquid releases.

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g.

In addition, the program DOSUM (DM) is used to search the results files of DSlLI to find the maximum liquid pathway individual doses. The highest exposures are then printed in a summary table. Each line is compared with the appropriate dose limit. The table provides a concise summary of off-site environmental dose calculations for inclusion in Annual Radioactive Effluent Release Reports, required by Reg. Guide 1.21.

The performance of each surveillance requirement must be within the specified time interval with a maximum allowable extension not to exceed 25 % of the specified surveillance interval.

3.2

• Limits of Operation and Surveillances of the Effluent Release Points

3. 2.1 Radioactive Liquid Effluent Monitoring Instrumentation

a.

The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, are operable with their alarm/trip setpoints set to ensure that the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are not exceeded.

b.

The applicability of each channel is shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments.

c.

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are met without delay, suspend the release of radioactive liquid effluents monitored by the affected channel and reset or declare the monitor inoperable.

d.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the applicable action shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, with a maximum allowable extension not to exceed 25 % of the surveillance interval, excluding the initial performance.

e.

Determine the setpoints in accordance with the methodology described in step 3. 3.1, Liquid Monitors. Record the setpoints.

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f.

Demonstrate each radioactive liquid effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Attachment 3.3, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

BASES - LIQUID The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CPR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11. 3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

Due to the location of the ESW monitors, outlet line of containment spray heat exchanger (typically out of service), weekly sampling is required of the ESW system for radioactivity.

This is necessary to ensure monitoring of a CCW to ESW system leak. [Ref 5.2. lhh]

3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation

a.

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, are operable with their alarm/trip setpoints set to ensure that the limits of step 3.2.4a, Dose Rate, are not exceeded.

b.

The applicability of each channel is shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation.

c.

With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of step 3.2.4a, Dose Rate, are met, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel and reset or declare the channel inoperable.

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d.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in.4, Radioactive Gaseous Effluent Monitoring Instrumentation, with a maximum allowable extension not to exceed 25 % of the surveillance interval, excluding the initial performance.

This surveillance requirement does not apply to the waste gas holdup system hydrogen and oxygen monitors, as their setpoints are not addressed in this document.

e.

Determine the setpoints in accordance with the methodology as described in step 3.3.2, Gaseous Monitors. Record the setpoints.

f.

Demonstrate each radioactive gaseous process or effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Attachment 3.5, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

BASES - GASEOUS The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this

• instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3.2.3 Liquid Effluents

a.

Concentration Excluding Releases via the Turbine Room Sump (TRS)

Discharge

1.

Limit the* concentration of radioactive material released via the Batch Release Tanks or Plant Continuous Releases ( excluding only TRS discharge to the Absorption Pond) to unrestricted areas to the concentrations in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, limit the concentration to 2E-4 µCi/ml total activity.

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2.

With the concentration of radioactive material released from the site via the Batch Release Tanks or Plant Continuous Releases ( other than the TRS to the Absorption Pond) exceeding the above limits, without delay restore the concentration to within the above limits.

3.

Sample and analyze radioactive liquid wastes according to the sampling and analysis program of Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

4.

Use the results of radioactive analysis in accordance with the*

methods of this document to assure that all concentrations at the point of release are maintained within limits.

b.

Concentration of Releases from the TRS Discharge

1.

Limit releases via the TRS discharge to the on-site Absorption Pond to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, limit the concentration to 2E-4 µCi/ml total activity.

2.

With releases from the TRS exceeding the above limits, perform a dose projection due to liquid releases to UNRESTRICTED AREAS to determine if the limits of step 3.2.3c.1 have been exceeded. If the dose limits have been exceeded, follow the directions in step 3.2.3c.2, as applicable.

3.

Sample and analyze radioactive liquid wastes according to the program in Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

4.

Use the results of radioactive analysis in accordance with the methods of this document to assure that all concentrations at the point of release are maintained within the limits stated above.

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c.

Dose

1.

Limit the dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas during any calendar quarter to ::::: 1.5 mrem/unit to the total body and to :::; 5 mrem/unit to any organ, and during any calendar year to ::S: 3 mrem/unit to the total body and to :::; 10 mrem/unit to any organ.

2.

With the calculated release of radioactive materials in liquid effluents exceeding ten times any of the limits in Steps 3.2.3a or 3.2.3b, or exceeding 3.2.3c.1 above, prepare and submit a Written Report, pursuant to 10 CFR 20.2203, within 30 days after learning of the event. This report must describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:

a)

Estimate of each individual's dose. This is to include the radiological impacts on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act (applicable due to Lake Township water treatment facility),

b)

Levels of radiation and concentration of radioactive material

involved, c)

Cause of elevated exposures, dose rates or concentrations,

-AND-d)

Corrective steps taken or planned to ensure against recurrence, including schedule for achieving conformance with applicable limits.

These reports must be formatted in accordance with PMP-7030-001-002, Licensee Event Reports, Special and Routine Reports, even though this is not an LER.

3.

Determine cumulative and projected dose contributions from liquid effluents in accordance with this document at least once per 31 days.

Dose may be projected based on estimates from previous monthly projections and current or future plant conditions.

d.

Liquid Radwaste Treatment System

1.

Use the liquid rad waste treatment system to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site when averaged over 31 days, would exceed 0.12 mrem (0.06 mrem/unit x 2 units) to the total body or 0.4 mrem (0.2 mrem/unit x 2 units) to any organ.

2.

Project doses due to liquid releases to UNRESTRICTED AREAS at least once per 31 days, in accordance with this document.

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e.

During times of primary to secondary leakage, the use of the startup flash tank should be minimized to reduce the release of curies from the secondary system and to maintain the dose to the public ALARA.

Drainage of high conductivity water (Component Cooling Water and ice melt water containing sodium tetraborate) shall be evaluated to decide whether it should be drained to waste (small volumes only), the Turbine Room Sump (low activity water only) or routed without demineralization processing to a monitor tank for release. This is necessary in order to minimize the detrimental effect that high conductivity water has on the radioactive wastewater demineralization system. The standard concentration and volume equation can be utilized to determine the impact on each method and is given here. The units for concentration and volume need to be consistent across the equation:

Where:

C Vi Ca Va Ct Vt

=

=

=

=

=

=

( C)(Vi) + ( Ca)(Va) = ( Cr)(Vi) the initial concentration of the system being added to the initial volume of the system being added to the concentration of the water that is being added to the system the volume of the water that is being added to the system the final concentration of the system after the addition the final volume of the system after the addition The intent is to keep the:

WDS below 500 µmhos/cc.

TRS below lE-5 µC/cc.

Monitor Tank release ALARA to members of the public.

Wastewater leakage into the liquid waste disposal system will be monitored routinely. In the event the leak rate is determined to be over two gallons per minute (the assumed plant design leakage based on the original 2 gpm waste evaporator), increased scrutiny will be placed on locating in-leakage, timeliness of job order activities, and/or activities causing increased production of waste water.

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Page 21 of 98 OFF-SITE DOSE CALCULATION MANUAL BASES - CONCENTRATION This specification is provided to ensure the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures greater than 1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and 2) the limits of 10 CFR Part 20. The concentration limit for noble gasses is based upon the assumption that Xe-135 is the controlling radionuclide and its Effluent Concentration Unit in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological Protection (ICRP) Publication 2.

DOSE This specification is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits implement the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents, will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.

This specification applies to the release of liquid effluents from each reactor at the site. The liquid effluents from the shared system are proportioned among the units sharing the system.

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. LIQUID WASTE TREATMENT The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section II. D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3.2.4 Gaseous Effluents

a.

Dose Rate

1.

Limit the dose rate due to radioactive materials released in gaseous effluents from the site to s 500 mrem/yr to the total body and s 3000 mrem/yr to the skin for noble gases. Limit the dose rate due to all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days to s 1500 mrem/yr to any organ.

2.

With the dose rate(s) exceeding the above limits, without delay decrease the release rate to within the above limit(s).

3.

Determine the dose rate due to noble gases in gaseous effluents to be within the above limits in accordance with the methods and procedures described in this document.

4.

Determine the dose rate due to radioactive materials, other than noble gases, in gaseous effluents to be within the above limits in accordance with the methods and procedures of this document by obtaining representative samples and performing analyses in accordance with the sampling and analysis program in Attachment 3.7, Radioactive Gaseous Waste Sampling and Analysis Program.

b.

Dose - Noble Gases

1.

Limit the air dose in unrestricted areas due to noble gases released in gaseous effluents during any calendar quarter, to s 5 mrad/unit for gamma radiation and s 10 mrad/unit for beta radiation and during any calendar year, to s 10 mrad/unit for gamma radiation and s 20 mrad/unit for beta radiation.

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2.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed in step 3.2.3c.2, within 30 days after learning of the event.

3.

Determine cumulative and projected dose contributions for the total time period in accordance with this document at least once every 31 days.

c.

Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form

1.

Limit the dose to a MEMBER OF THE PUBLIC from radioiodine, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas (site boundary) to the following:

a)

During any calendar quarter to less than or equal to 7.5 mrem/unit to any organ b)

During any calendar year to less than or equal to 15 mrem/unit to any organ.

2.

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed in step 3.2.3c.2, within 30 days after learning of the event.

3.

Determine cumulative and projected dose contributions for the total time period in accordance with this document at least once every 31 days.

d, Gaseous Radwaste Treatment

1.

The UFSAR (Updated Final Safety Analysis Report) states that radioactive waste gas should be held for 45 days of decay time.

2.

Use the gaseous radwaste treatment system and the ventilation exhaust treatment system to reduce radioactive materials in gaseous wastes prior to their discharge when projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days, would exceed 0.4 mrad (0.2 mrad/unit x 2 units) for gamma radiation and 0.8 mrad (0.4 mrad/unit x 2 units) for beta radiation.

Use the ventilation exhaust treatment system to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days would exceed 0.3 mrem/unit to any organ.

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3.

Project doses due to gaseous releases to UNRESTRICTED AREAS at least once per 31 days in accordance with this document.

BASES -- GASEOUS EFFLUENTS This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an unrestricted area, either at or beyond the site boundary in excess of the design objectives of appendix I to 10 CPR 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and 11.C design objectives of appendix I to 10 CPR 50.

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor*

above that for the site boundary. The specified instantaneous release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to ::;:; 500 mrem/yr to the total body or to ::;:; 3000 mrem/yr to the skin.

These instantaneous release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to ::;:; 1500 mrem/yr. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CPR 20, Appendix B, Table 2, Column 1.

This specification applies to the release of gaseous effluents from all reactors at the site. The gaseous effluents from the shared system are proportioned among the units sharing that system.

DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections 11.B, III.A, and IV.A of Appendix I, 10 CPR Part 50. The dose limits implement the guides set forth in Section 11.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",

Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary will be based upon the historical average atmospherical conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

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Page 25 of 98 OFF-SITE DOSE CALCULATION MANUAL DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CPR Part 50. The dose limits are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable",.

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, July 1977. These equations also provide the methodology for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides, other than noble gases, are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,

3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

GASEOUS WASTE TREATMENT The operability of the gaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

This specification implements the requirements of 10 CPR Part 50.36a, General Design Criterion Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section II.D of Appendix I to 10 CPR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guides forth in Sections II.B and II.C of Appendix I, 10 CPR Part 50, for gaseous effluents.

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a.

The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to :::; 25 mrem to the total body or any organ (except the thyroid, which is limited to::; 75 mrem) over a period of 12 consecutive months.

b.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of steps 3.2.3c (Dose), 3.2.4b (Dose - Noble Gases), or 3.2.4c (Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form) during any calendar quarter, perform the following:

Investigate and identify the causes for such release rates; Define and initiate a program for corrective action; Report these actions to the NRC within 30 days from the end of the quarter during which the release occurred.

IF the estimated dose(s) exceeds the limits above, and IF the release condition resulting in violation has not already been corrected prior to violation of 40 CFR 190, THEN include in the report a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR 50, as addressed in other sections of this document.

c.

Determine cumulative dose contributions from liquid and gaseous effluents in accordance with this document (including steps 3.2.3c

[Dose], 3.2.4b [Dose - Noble Gases], or 3.2.4c [Dose - Iodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form]).

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Page 27 of 98 OFF-SITE DOSE CALCULATION MANUAL BASES -- TOTAL DOSE This specification is provided to meet the dose limitations of 40 CPR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CPR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action, which should result in the limitations of dose to a member of the public for 12 consecutive months to within the 40 CPR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to any member of the public from other uranium fuel cycle sources is negligible with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CPR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CPR 190 have not already been corrected, in accordance with the provision of 40 CPR 190.11), is considered to be a timely request and fulfills the requirements of 40 CPR 190 until NRC staff action is completed.

An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation, which is part of the nuclear fuel cycle.

3. 3 Calculation of Alarm/Trip Setpoints The alarm and trip setpoints are to provide monitoring, indication, and control of liquid and gaseous effluents. The setpoints are used in conjunction with sampling programs to assure that the releases are kept within the limits of 10 CPR 20, Appendix B, Table 2.

Establish setpoints for liquid and gaseous monitors. Depending on the monitor function, it would be a continuous or batch monitor. The different types of monitors are subject to different setpoint methodologies.

One variable used in setpoint calculations is the multiple release point (MRP) factor.

The MRP is a factor used such that when all the releases are integrated, the applicable LIMIT value will not be exceeded. The MRP is determined such that the sum of the MRP's for that effluent type (liquid or gaseous) is less than or equal to 1. The value of the MRP is arbitrary, and it should be assigned based on operational performance. The values of the MRP's for each liquid release point are given in Attachment 3.8, Multiple Release Point Factors for Release Points.

The Site stance on instrument uncertainty is taken from HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits, which states the NRC position is the result of a valid measurement obtained by a method, which provides a reasonable demonstration of compliance. This value should be accepted and the uncertainty in that measured value need not be considered.

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3. 3.1 Liquid Monitors Establish liquid monitor setpoints for each monitor of the liquid effluent release systems. A schematic of the liquid effluent release systems is shown as.9, Liquid Effluent Release Systems. A list of the Plant Liquid Effluent Parameters is in Attachment 3.10, Plant Liquid Effluent Parameters.

The details of each system design and operation can be found in the system descriptions. The setpoints are intended to keep releases within the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Determine setpoints using either the batch or the continuous methodology.

a.

Liquid Batch Monitor Setpoint Methodology

1.

There is only one monitor (two following the RMS upgrades) used on the Waste Disposal System for liquid batch releases. This monitor is identified as RRS-1000 (RRS-1001-A [primary] and RRS-1001-B [back-up] following upgrade). Steam Generator Blowdown radiation monitors also can be used to monitor batch releases while draining steam generators. The function of these monitors is to act as a check on the sampling program. The sampling program determines the nuclides and concentrations of those nuclides prior to release. The discharge and dilution flow rates are then adjusted to keep the release within the limits of 10 CFR 20. Based on the concentrations of nuclides in the release, the count rate on the monitor can be predicted. The high alarm setpoint can then be set above the predicted value up to the maximum setpoint of the system.

2.

The radioactive concentration of each batch of radioactive liquid waste to be discharged is determined prior to each release by sampling and analysis in accordance with Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

3.

The allowable release flow rates are determined in order to keep the release concentrations within the requirements of 10 CFR 20, Appendix B, Table 2, Column 2. The equation to calculate the flow rate is from Addendum AAl of NUREG-0133:

Where:

[L C

]*_1_5:,F+ f LIMIT; MRP.

Ci = the concentration of nuclide "i" in µCi/ml LIMITi = the 10 CFR 20, Appendix B, Table 2, Column 2 limit of nuclide "i" in µCi/ml f

= the effluent flow rate in gpm (Attachment 3.10, Plant Liquid Effluent Parameters)

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= the dilution water flow rate as estimated prior to release.

The dilution flow rate is a multiple of 230,000 gpm depending on the number of circulation pumps in operation.

MRP = the multiple release point factor. A factor such that when all the release points are operating at one time the limits of 10 CPR 20 will not be exceeded.

4.

This equation must be true during the batch release. Before the release is started, substitute the maximum effluent flow rate and the minimum dilution flow rate for f and F, respectively. If the equation is true, the release can proceed with those flow rates as the limits of operation. If the equation is not true, the effluent flow rate can be reduced or the dilution flow rate can be increased to make the equation true. This equation may be rearranged to solve for the maximum effluent release flow rate (f).

5.

The setpoint is used as a quality check on the sampling program.

The setpoint is used to stop the effluent flow when the monitor reading is greater than the predicted value from the sampling program. The predicted value is generated by converting the effluent concentration for each gamma emitting radionuclide to counts per unit of time as per Attachment 3.11, Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline and Mirian Liquid Monitors, or Attachment 3.12, Counting Efficiency for R-19, l/2-DRA-300, R-24, and l/2-DRA-353. The sum of all the counts per unit of time is the predicted count rate. The predicted count rate can then be multiplied by a factor to determine the high alarm setpoint that will provide a high degree of conservatism and eliminate spurious alarms.

b.

Liquid Continuous Monitor Setpoint Methodology

1.

There are eight monitors used as potential continuous liquid release monitors. These monitors are used in the steam generator blowdown (SGBD), blowdown treatment (BOT), and essential service water (ESW) systems.

2.

These Westinghouse monitors (R) are being replaced by Eberline monitors (DRS) and are identified as: (Mirian monitors [DRA] are replacing both Westinghouse and Eberline)

R-19 or DRS 3100/4100 for SGBD (DRA-300 for SGBD)

R-24 or DRS 3200/4200 for BDT (DRA-353 for BDT)

The function of these monitors is to assure that releases are kept within the concentration limits of 10 CPR 20, Appendix B, Table 2, Column 2, entering the unrestricted area following dilution.

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3.

The monitors on steam generator blowdown and blow down treatment systems have trip functions associated with their setpoints.

Essential service water monitors are equipped with an alarm function only and monitor effluent in the event the Containment Spray Heat Exchangers are used.

4.

The equation used to determine the setpoint for continuous monitors is from Addendum AAl of NUREG-0133:

C* Ejf

• MRP

• F*SF Sp~ _

___..;..c.._ _____

f Where:

Sp = setpoint of monitor ( cpm)

C

= 5E-7 µCi/ml, maximum effluent control limit from 10 CPR 20, Appendix B, Table 2, Column 2 of a known possible nuclide in effluent stream. (The limiting nuclide shall be evaluated annually by reviewing current nuclides against historical ones in order to determine if one with a more restrictive effluent concentration limit than Sr90 is found. The concentration limit shall be adjusted appropriate! y.)

-OR-if a mixture is to be specified, Ic I

C LIMIT; Eff = Efficiency, this information is located in Attachment 3.11, Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline and Mirian Liquid Monitors, through Attachment 3.13, Counting Efficiency for R-20, R-28, 1-WRA-713, 2-WRA-714, 1-WRA-717, and 2-WRA-718, for the specific monitors.

For Eberline and Mirion monitors, the efficiency is nuclide specific.and the calculation changes slightly to:

I(C* E.ff)

---

'- replaces C

• Ejf I

C LIMIT;

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Page 31 of 98 OFF-SITE DOSE CALCULATION MANUAL MRP = multiple release point factor. A factor such that when all the release points are operating at one time the limits of 10 CFR 20 will not be exceeded (Attachment 3.8, Multiple Release Point Factors for Release Points). The MRP for ESW monitors is set to 1.

F

= dilution water (circ water) flow rate in gpm obtained from Attachment 3.10, Plant Liquid Effluent Parameters.

For routine operation, the setpoint should be calculated using the minimum dilution flow rate of 230,000 gpm.

SF = Safety Factor, 0.9.

f

= applicable effluent release flow rate in gpm. For routine operation, the setpoint should be calculated using maximum effluent flow rate (Attachment 3. l O, Plant Liquid Effluent Parameters).

3.3.2 Gaseous Monitors NOTE:

For the purpose of implementing Step 3.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation, and Substep 3.2.4a, Dose Rate, the alarm setpoints for gaseous effluents released into unrestricted areas will be established using the following methodology. In addition, the above steps do not apply to instantaneous alarm and trip setpoints for integrating radiation monitors sampling radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. A schematic of the gaseous effluent release systems is presented in Attachment 3.14, Gaseous Effluent Release Systems. Attachment 3.15, Plant Gaseous Effluent Parameters, presents the effluent flow rate parameter(s).

Gaseous effluent monitor high alarm setpoints will routinely be established at a fraction of the maximum allowable setpoint (typically 10% of the setpoint) for ALARA purposes. Alert alarms will normally be set to provide adequate indications of small changes in radiological conditions.

IF the setpoint calculation methodology changes or the associated factors change for Unit Vent, Air Ejector and/or Gland Seal monitors, THEN initiate a review by Emergency Planning to ensure that the requirements of 10 CFR 50.54 (q) are maintained.

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a.

Plant Unit Vent

1.

The gaseous effluents discharged from the plant vent will be monitored by the plant vent radiation monitor low (normal) range noble gas channel [Tag No. VRS-1505 (Unit 1), VRS-2505 (Unit 2)]

(Mirion monitors VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/ VRS-2505B for Unit 2) to assure that applicable alarms and trip actions (isolation of gaseous release) will occur prior to exceeding the limits in step 3.2.4, Gaseous Effluents. The alarm setpoint values will be established using the following unit analysis equation:

Where:

Sp

= the maximum setpoint of the monitor in µCi/cc for release point p, based on the most limiting organ SF = an administrative operation safety factor, less than 1. 0 MRP = a weighted multiple release point factor(~ 1.0), such that when all site gaseous releases are integrated, the applicable dose will not be exceeded based on the release rate of each effluent point. The MRP is an arbitrary value based on the ratio of the release rate or the volumetric flow rate of each effluent point to the total respective flow rate value of the plant and will be consistent with past operational experience.

The MRP is computed as follows:

Compute the average release rate, Qp, ( or the volumetric flow rate, fr) from each release point p.

Compute }:Qp ( or }:fp) for all release points.

Ratio Qp/}:Qp (or fp/Lfp) for each release point.

This ratio is the MRP for that specific release point Repeat the above bullets for each of the site's eight gaseous release points.

FP = the maximum volumetric flow rate of release point "p",

at the time of the release, in cc/sec. The maximum Unit Vent flow rate, by design, is 186,600 cfm for Unit 1 and 143,400 cfm for Unit 2.

DLi = dose rate limit to organ "j" in an unrestricted area (mrem/yr).

Based on continuous releases, the dose rate limits, DLi, from step 3.2.4a, Dose Rate, are as follows:

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Page 33 of 98 OFF-SITE DOSE CALCULATION MANUAL Total Body ::; 500 mrem/year Skin::; 3000 mrem/year Any Organ::; 1500 mrem/year x I Q = The worst case annual average relative concentration in the applicable sector or area, in sec/m3 (see Attachment 3.16, 10 Year Average of 1995-2004 Data).

Wi = weighted factor for the radionuclide:

Where:

Ci = concentration of the most abundant radionuclide "i" Ck = total concentration of all identified radionuclides in that release pathway. For batch releases, this value may be set to 1 for conservatism.

DCFij = dose conversion factor used*to relate radiation dose to organ "j", from exposure to radionuclide "i" in mrem m3 I yr µCi. See following equations.

The dose conversion factor, DCFij, is dependent upon the organ of concern.

For the whole body:

DCFij = Ki Where:

Ki = whole body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem m3 I yr µCi. See.18, Dose Factors.

For the skin:

DCFij =Li+ l.lMi Where:

Li = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem m3 I yr µCi. See Attachment 3.18, Dose Factors.

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Page 34 of 98 OFF-SITE DOSE CALCULATION MANUAL 1.1 = the ratio of tissue to air absorption coefficient over the energy range of photons of interest. This ratio converts absorbed dose (mrad) to dose equivalent (mrem).

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad m3 / yr µCi. See.18, Dose Factors.

For the thyroid, via inhalation:

DCFij = Pi Where:

Pi = the dose parameter, for radionuclides other than noble gas, for the inhalation pathway in mrem m3 / yr µCi (and the food and ground path, as appropriate).

See Attachment 3.18, Dose Factors.

2.

The plant vent radiation monitor low (normal) range noble gas high alarm channel setpoint, Sp, will be set such that the dose rate in unrestricted areas to the whole body, skin and thyroid ( or any other organ), whichever is most limiting, will be less than or equal to 500 mrem/yr, 3000 mrem/yr, and 1500 mrem/yr respectively.

3.

The thyroid dose is limited to the inhalation pathway only.

4.

The plant vent radiation monitor low (normal) range noble gas setpoint, Sr, will be recomputed whenever gaseous releases like Containment Purge, Gas Decay Tanks and CVCS HUTs are discharged through the plant vent to determine the most limiting organ.

5.

The high alarm setpoint, SP, may be established at a lower value than the lowest computed value via the setpoint equation.

6.

Containment Pressure Reliefs will not have a recomputed high alarm setpoint, but will use the normal high alarm setpoint due to their randomness and the time constraints involved in recomputation.

7.

At certain times, it may be desirable to increase the high alarm setpoint, if the vent flow rate is decreased. This may be accomplished in one of two ways.

Max Cone (µCi/cc)* Max Flowrate (cfin) 71.r M

,+;,,,,

---

'-'----'-------.;._:_-'- = 1veW ax Cpu New Max Concentration ( µCi/cc)

-OR-

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J\\r M

c*1

---

'---------'-'---'-- = 1vew axµ 11cc New Max Flowrate (cfin)

b.

Waste Gas Storage Tanks

1.

The gaseous effluents discharged from the Waste Gas System are monitored by the plant vent radiation monitor noble gas channels VRS-1505 and VRS-2505 (Mirion monitors VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/ VRS-2505B for Unit 2).

2.

In the event of a high radiation alarm, an automatic termination of the release from the waste gas system will be initiated from the plant vent radiation monitor low (normal) range noble gas channel (VRS-1505 or VRS-2505) (Mid.on monitors VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/ VRS-2505B for Unit 2).

Therefore, for any gaseous release configuration, which includes normal operation and waste gas system gaseous discharges, the alarm setpoint of the plant vent radiation monitor will be recomputed to determine the most limiting organ based on all gaseous effluent source terms.

Chemical and Volume Control System Hold Up Tanks (CVCS HUT), containing high gaseous oxygen concentrations, may be released under the guidance of waste gas storage tank utilizing approved Operations' procedures..

3.

It is normally prudent to allow 45 days of decay prior to releasing a Gas Decay Tank (GDT). There are extenuating, operational circumstances that may prevent this from occurring. Under these circumstances, such as high oxygen concentration creating a combustible atmosphere, it is prudent to waive the 45-day decay for safety's sake.

c.

Containment Purge and Exhaust System

1.

The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust System are monitored by the plant vent radiation monitor noble gas channels (VRS-1505 for Unit 1, VRS-2505 for Unit 2) (Mirian monitors VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/

VRS-2505B for Unit 2) ; and alarms and trip actions will occur prior to exceeding the limits in step 3.2.4a, Dose Rate.

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2.

For the Containment System, a continuous air sample from the containment atmosphere is drawn through a closed, sealed system to the radiation monitors (Tag No. ERS-1300/1400 for Unit 1 and ERS-2300/2400 for Unit 2). During purges, these monitor setpoints will give a Purge and Exhaust Isolation signal upon actuation of high alarm setpoints for particulate and noble gas channels. The sample is then returned to containment. Grab sample analysis is performed for a Containment purge before release.

3.

The Upper Containment area is monitored by normal range area gamma monitors (Tag No. VRS-1101/1201 for Unit 1 and VRS-2101/2201 for Unit 2), which also give Purge and Exhaust Isolation Trip signals upon actuation of their high alarm.

4.

For the Containment Pressure Relief System, no sample is routinely taken prior to release, but a sample is obtained twice per month.

5.

The containment airborne and area monitors, upon actuation of their high alarm, will automatically initiate closure of the Containment and Instrument Room purge supply and exhaust duct valves and containment pressure relief system valves. Complete trip of all isolation control devices requires high alarm of one of the two Train A monitors (ERS-1300/2300 or VRS-1101/2101) and one of the two Train B monitors (ERS-1400/2400 or VRS-1201/2201).

d.

Steam Jet Air Ejector System (SJAE)

1.

The gaseous effluents from the Steam Jet Air Ejector System discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1900 for Unit 1 and SRA-2900 for Unit 2). The monitor will alarm prior to exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the Condenser Air Ejector System monitor will be based on the maximum air ejector exhaust flow rate, (Attachment 3.15, Plant Gaseous Effluent Parameters). The alarm setpoint value will be established using the following unit analysis equation:

Where:

Ss1AE

= the maximum setpoint, based on the most limiting organ, in µCi/cc and where the other terms are as previously defined

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e.

Gland Seal Condenser Exhaust

1.

The gaseous effluents from the Gland Seal Condenser Exhaust discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1800 for Unit 1 and SRA-2800 for Unit 2). The radiation monitor will alarm prior to exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the GSCE monitor will be based on the maximum condenser exhaust flow rate (1260 CFM for Unit 1, 2754 CFM each for the two Unit 2 vents).

The alarm setpoint value will be established using the following unit analysis equation:

SF*MRP*DL*

S J

GSCE-Fp

• x!Q*I(w;* DCFij)

Where:

SosCE the maximum setpoint, based on the most limiting organ, in µCi/cc and where the other terms are as previously defined 3.4 Radioactive Effluents Total Dose 3.4.1 The cumulative dose contributions from liquid and gaseous effluents will be determined by summing the cumulative doses as derived in steps 3.2.3c (Dose), 3.2.4b (Dose - Noble Gases), and 3.2.4c (Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form) of this procedure. Dose contribution from direct radiation exposure will be based on the results of the direct radiation monitoring devices located at the REMP monitoring stations, and reflects direct dose both from the Dry Cask Storage Facility (ISFSI) licensed under Holtech International and both units of Cook.

See NUREG-0133, section 3.8.

3.5 Radiological Environmental Monitoring Program (REMP) 3.5.1 Purpose of the REMP

a.

The purpose of the REMP is to:

Establish baseline radiation and radioactivity concentrations in the environs prior to reactor operations,

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Page 38 of 98 OFF-SITE DOSE CALCULATION MANUAL Monitor critical environmental exposure pathways, Determine the radiological impact, if any, caused by the operation of the Donald C. Cook Nuclear Plant upon the local environment.

Assist with fulfilling the requirements of the Groundwater Protection Initiative (GPI).

b.

The first purpose of the REMP was completed prior to the initial operation of either of the two nuclear units at the Donald C. Cook Nuclear Plant Site. The remaining purposes of the REMP are an on-going operation and as such various environmental media and exposure pathways are examined. The various pathways and sample media used are delineated in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies. Included is a list of the sample media, analysis required, sample stations, and frequency requirements for both collection and analysis. Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, defines the scope of the REMP for the Donald C. Cook Nuclear Plant.

3.5.2 Conduct of the REMP [Ref. 5.2.lv]

a.

Conduct sample collection and analysis for the REMP in accordance with.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, Attachment 3.20, Maximum Values for Lower Limits of Detections A*B - REMP, and.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples. These are applicable at all times. The on-site monitoring locations are shown on Attachment 3.22, On-Site Monitoring Location - REMP, and the off-site monitoring locations are shown on,23, Off-Site Monitoring Locations - REMP.

1.

Perform each surveillance requirement within the specified time interval in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, with a maximum allowable extension not to exceed 25 % of the surveillance interval.

2.

If an environmental sample cannot be collected in accordance with step 3.5.2a, submit a description of the reasons for deviation and the actions taken to prevent a reoccurrence as part of the Annual Radiological Environmental Operating Report (ARBOR).

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NOTE:

OFF-SITE DOSE CALCULATION MANUAL

3.

Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of automatic sampling equipment. If

• the deviation from the required sampling schedule is due to the malfunction of automatic sampling equipment, make every effort to complete the corrective action prior to the end of the next sampling period.

Only one report per event is required.

Radioactivity from sources other than plant effluents do not require a Special Report.

4.

IF any of the following conditions are identified:

A radionuclide associated with plant effluents is detected in any REMP sample medium AND its concentration exceeded the limits specified in Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples, More than one radionuclide associated with plant effluents is detected in any REMP sample medium AND the Total Fractional Level, when averaged over the calendar quarter, is greater than or equal to 1.

THEN complete the following steps, as applicable:

Submit a Special Report to the Nuclear Regulatory Commission within 30 days.

Submit a Special Report to designated state and local organizations for groundwater or surface water media which could be used as drinking water.

Evaluate the following items for inclusion in Special Reports:

1)

Release conditions

2)

Environmental factors

3)

Corrective actions

4)

Additional factors which may have contributed to the identified levels

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5.

WHEN submission of a Special Report to designated state and local organizations is required, THEN perform the following:

Communicate event specific information to designated state and local organization personnel by the end of the next business day.

Document the notification using PMP-6090-PCP-100, Data Sheet 2, Part 4 Radioactive Liquid Spill Which May Impact Groundwater.

Forward a copy of the notification to the Environmental Department Manager.

6; IF a currently sampled milk farm location becomes unavailable, THEN conduct a special milk farm survey within 15 days.

a)

IF the unavailable location was an indicator farm, THEN an alternate sample location may be established within eight miles of the Donald C. Cook Nuclear Plant, if one is available.

b) IF the unavailable location was a background farm, THEN an alternate sample location may be established greater than 15 but less than 25 miles of the Donald C. Cook Nuclear Plant in one of the less prevalent wind direction sectors, if one is available.

c)

IF a replacement farm is unobtainable and the total number of indicator farms is less than three or the background farms is less than one, THEN perform monthly vegetation sampling in lieu of milk sampling when vegetation is available.

BASES - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

The REMP provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. Thereby, this monitoring program supplements the radiological effluent monitoring program by verifying the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified REMP was effective for the first three years of commercial operation. Program changes may be initiated based on operational experience in accordance with the requirements of Technical Specification 5.5.1.c.

The detection capabilities, required by Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP, are the state-of-the-art for routine environmental measurements in industrial laboratories.

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Page 41 of 98 OFF-SITE DOSE CALCULATION MANUAL It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine analysis conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases; the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

3.5.3 Annual Land Use Census [Ref. 5.2.lv]

a.

Conduct a land use census and identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the ten land sectors within a distance of five miles.

b.

In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation (if available) may be performed as close to the site boundary as possible (within 5 miles) in each of two different direction sectors with the highest average deposition factor (D/Q) value.

c.

Conduct this land use census annually between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local agricultural authorities.

1.

With a land use census identifying a location(s), which yields a calculated dose or dose commitment greater than the values currently being calculated in this document, make appropriate changes to incorporate the new location(s) within 30 days, if possible.

BASES - LAND USE CENSUS This is provided to ensure changes in the use of unrestricted areas are identified and modifications to the monitoring program are made, if required by the results of the census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (that is, similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

3.5.4 lnterlaboratory Comparison Program

a.

In order to comply with Reg. Guides 4.1 and 4.15, the analytical vendor participates in an Interlaboratory Comparison Program, for radioactive materials. Address program results and identified deficiencies in the ARBOR.

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1.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the ARBOR.

BASES-INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.

3.6 Meteorological Model

3. 6.1 Three towers are used to determine the meteorological conditions at Donald C.

Cook Nuclear Plant. One of the towers is located at the Lake Michigan shoreline to determine the meteorological parameters associated with unmodified shoreline air. The data is accumulated by microprocessors at the tower sites and normally transferred to the central computer every 15 minutes.

3.6.2 The central computer uses a meteorological software program to provide atmospheric dispersion and deposition parameters. The meteorological model used is based on guidance provided in Reg. Guide 1.111 for routine releases. All calculations use the Gaussian plume model.

3. 7 Reporting Requirements

3. 7.1 Annual Radiological Environmental Operating Report (ARBOR)

a.

Submit routine radiological environmental operating reports covering the operation of the units during the previous calendar year prior to May 15 of each year. [Ref 5.2.lj, TS 5.6.2]

b.

Include in the ARBOR:

Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the reporting period.

A comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The results of the land use censuses required by step 3. 5. 3, Annual Land Use Census.

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Page 43 of 98 OFF-SITE DOSE CALCULATION MANUAL If harmful effects or evidence of irreversible damage are detected by the monitoring, provide in the report an analysis of the problem and a planned course of action to alleviate the problem.

Summarized and tabulated results of all radiological environmental samples taken during the reporting period. In the event that some results are not available for inclusion with the report, submit the report noting and explaining the reasons for the missing results.

Submit the missing data as soon as possible in a supplementary report.

A summary description of the REMP including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used.

A map of all sample locations keyed to a table giving distances and directions from one reactor.

The results of participation in the Interlaboratory Comparison Program required by step 3.5.4, Interlaboratory Comparison Program.

The results of non-REMP samples taken for informational purposes in support of non-program specific investigations, such as rainfall studies of tritium recapture for example.

3. 7. 2 Annual Radiological Effluent Release Report (ARERR)

a.

Submit routine ARERR covering the operation of the unit during the previous 12 months of operation prior to May 1 sc of each year. [Ref 5.2. lj, TS 5.6.3]

b.

Include in the ARERR a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Reg. Guide 1.21, "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B, thereof.

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c.

Submit in the ARERR prior to May 1st of each year and include a quarterly summary of hourly meteorological data collected during the reporting period.

This summary may be in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

Include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

Include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the reporting period. Include all assumptions used in making these assessments (that is, specific activity, exposure time and location) in these reports.

Use the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) for determining the gaseous pathway doses.

Inoperable radiation monitor periods exceeding 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence.

d.

Submit the ARERR [Ref. 5.2.lx] prior to May pt of each year and include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Reg. Guide 1.109, Rev.1.

e.

Include in the ARERR the following information for each type of solid waste shipped off-site during the report period:

Volume (cubic meters),

Total curie quantity (specify whether determined by measurement or estimate),

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Page 45 of 98 OFF-SITE DOSE CALCULATION MANUAL Principle radionuclides (specify whether determined by measurement or estimate),

Type of waste (example: spent resin, compacted dry waste, evaporator bottoms),

Type of container (example: LSA, Type A, Type B, Large Quantity),

-AND-Solidification agent (example: cement).

f.

Include in the ARERR unplanned releases of radioactive materials in gaseous and liquid effluent from the site to unrestricted areas on a quarterly basis.

g.

Include in the ARERR any change to this procedure made during the reporting period.

h.

Due to the site having shared gaseous and liquid waste systems dose calculations will be performed on a per site bases using the per unit values. This is ALARA and will ensure compliance with 40 CFR 141, National Primary Drinking Water Regulations. Unit specific values are site values divided by two.

1.

Include in the ARERR groundwater sample results taken that are in support of the Groundwater Protection Initiative (GPI) but are not part of the REMP.

3.8 10 CFR 50.75 (g) Implementation 3.8.1 Records of spills or other unusual occurrences involving the spread of contamination in and around the site. These records may be limited to instances when significant contamination remains after decontamination or when there is a reasonable likelihood that contaminants may have spread to inaccessible areas, as in the case of possible seepages.

3. 8. 2 These records shall include any known information or identification of involved nuclides, quantities, and concentrations.

3.8.3 This information is necessary to ensure all areas outside the radiological-restricted area are documented for surveying and remediation during decommissioning. There is a retention schedule item for 10 CFR 50.75(g) where this information is filed in Nuclear Documents Management to ensure all required areas are listed to prevent their omission.

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3. 9 Reporting/Management Review

3. 9. 1 Incorporate any changes to this procedure in the ARERR.

3.9.2 Update this procedure when required for changes made to the Radiation Monitoring System, its instruments, or the specifications of instruments.

3. 9. 3 Review or revise this procedure as appropriate based on the results of the land use census and REMP.

3. 9.4 Consider any changes to this procedure for potential impact on other related

. Department Procedures.

3.9.5 Review the past year's meteorological data during the first quarter of each year and update the ODCM as necessary. Review Attachment 3.16, 10 Year Average of 1995-2004 Data, and document using Attachment 3.17, Annual Evaluation of x/Q and D/Q Values For All Sectors. The x IQ and DI Q values will be processed using +/- 3 standard deviations of the data and evaluated against the 10 year annual average data. Documentation is done by completing Attachment 3.17, Annual Evaluation of x/Q and D/Q Values For All Sectors, and filed in accordance with the retention schedule.

4 FINAL CONDITIONS 4.1 None.

5 REFERENCES 5.1 Use

References:

5.1.1 "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Off-Site Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01)", United States Nuclear Regulatory Commission, January 31, 1989 5.1.2 12-THP-6010-RPP-601, Preparation of the Annual Radioactive Effluent Release Report 5.1.3 12-THP-6010-RPP-639, Annual Radiological Environmental Operating Report (ARBOR) Preparation And Submittal 5.1. 4 PMP-6090-PCP-100, Spill Response-Oil, Polluting, Hazardous Materials, and Radioactive Spills

Information I

PMP-6010-0SD-001 I

Rev. 26 I

Page 47 of 98 OFF-SITE DOSE CALCULATION MANUAL 5.2 Writing

References:

5.2.1 Source

References:

a.

10 CFR 20, Standards for Protection Against Radiation

b.

10 CFR 50, Domestic Licensing of Production and Utilization Facilities

c.

PMI-6010, Radiation Protection Plan

d.

NUREG-0472

e.

NUREG-1301

f.

NUREG-0133

g.

Regulatory Guide 1.109, non-listed parameters are taken from these data tables

h.

Regulatory Guide 1.111

i.

Regulatory Guide 1.113

j.

Updated Final Safety Analysis Report (UFSAR)

k.

Technical Specifications 5.4.1.e, 5.5.1.c, 5.5.3, 5.6.2, and 5.6.3

1.

• Final Environmental Statement Donald. C. Cook Nuclear Plant, August 1973

m. NUREG-0017

n.

ODCM Setpoints for Liquid [and Gaseous] Effluent Monitors (Bases),

ENGR 107-04 8112.1 Environs Rad Monitor System

o.

HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits

p.

Watts - Bar Jones (WBJ) Document, R-86-C-001, The Primary Calibration of Eberline Instrument Corporation SPING - 3/4 Low, Mid, and High Range Noble Gas Detectors

q.

WBJ Document, R-86-C-003, The Primary Calibration of Eberline Instrument Corporation DAM-4 and Water Monitor

r.

40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations

s.

NRC Commitment 6309 (N94083 dated 11/10/94)

t.

NRC Commitment 1151

u.

NRC Commitment 1217

Information I

PMP-6010-0SD-001 I

Rev. 26 OFF-SITE DOSE CALCULATION MANUAL

v.

NRC Commitment 3240

w. NRC Commitment 3850

x.

NRC Commitment 4859

y.

NRC Commitment 6442

z.

NRC Commitment 3768 aa. DIT-B-00277-00, HVAC Systems Design Flows bb. Regulatory Guide 1.21 cc. Regulatory Guide 4.1 I

Page 48 of 98 dd. 1-2-V3-02-Calc #4, Unit Vent Sample Flow rate for isokinetic particulates and Iodine sampling ee. HPS N13.30-1996, Appendix A Rationale for Methods of Determining Minimum Detectable Amount (MDA) and Minimum Testing Level (MDL ff. DIT-B-01971-00, Dose Factors for Radioactive Particulate Gaseous Effluents Associated with the Child by the Inhalation Pathway gg. DIT-B-01987-00, Ground Plane & Food Dose Factors Pi for Radioiodines and Radioactive Particulate Gaseous Effluents hh. NRC Commitment 1010 ii.

NEI 07-07 Groundwater Protection Initiative jj. ANI 07-01 Potential for Unmonitored and Unplanned Off-Site Releases of Radioactive Material kk. RD-16-03, Mirion MCNPX Analysis Report

5. 2. 2 General References

a.

Cook Nuclear Plant Start-Up Flash Tank Flow Rate letter from D. L.

Boston dated January 21, 1997

b.

Letter from B.P. Lauzau, Venting of Middle CVCS Hold-Up Tank Directly to Unit Vent, May 1, 1992

c.

AEP Design Information Transmittal on Aux Building Ventilation Systems

d.

PMP-4030.EIS.001, Event-Initiated Surveillance Testing

Information I

PMP-6010-0SD-001 I

Rev. 26 I

Page 49 of 98 OFF-SITE DOSE CALCULATION MANUAL

e.

Environmental Position Paper, Fe Impact on Release Rates, approved 3/14/00

f.

Environmental Position Paper, Methodology Change from Sampling Secondary System Gaseous Effluents for Power Changes Exceeding 15% within 1 hr to Responding to Gaseous Alert Alarms, approved 4/4/00.

• g.

CR 02150078, RRS-1000 efficiency curve usage

h.

Environmental Position Paper, Unit Vent Compensatory Sampling, approved 4/ 14/05

Information PMP-6010-0SD-001 I

Rev. 26 Page 50 of 98 OFF-SITE DOSE CALCULATION MANUAL.1 Dose Factors for Various Pathways Pages:

50 - 53 R.i Dose Factors PATHWAY Nuclide Ground Vegetable Meat Cow Milk Goat Milk Inhalation H-3 O.OE+OO 4.0E+03 3.3E+02 2.4E+03 4.9E+03 l.3E+03 C-14 O.OE+OO 3.5E+06 5.3E+05 3.2E+06 3.2E+06 3.6E+04 Cr-51 5.4E+06 l.1E+07 l.5E+06 6.9E+06 8.3E+05 2.IE+04 Mn-54 l.6E+09 9.4E+08 2.1E+07 2.9E+07 3.5E+06 2.0E+06 Fe-59 3.2E+08 9.6E+08 l.7E+09 3.1E+08 4.0E+07 1.5E+06 Co-58 4.4E+08 6.0E+08 2.9E+08 8.4E+07 l.OE+07 l.3E+06 Co-60 2.5E+10 3.2E+09 1.0E+09 2.7E+08 3.2E+07 8.6E+06 Zn-65 8.5E+08 2.7E+09 9.5E+08 l.6E+l0 l.9E+09 l.2E+06 Sr-89 2.5E+04 3.5E+l0 3.8E+08 9.9E+09 2.lE+lO 2.4E+06 Sr-90 O.OE+OO 1.4E+l2 9.6E+09 9.4E+10 2.0E+l l 1.1E+08 Zr-95 2.9E+08 l.2E+09 l.5E+09 9.3E+05 l.1E+05 2.7E+06 Sb-124 6.9E+08 3.0E+09 4.4E+08 7.2E+08 8.6E+07 3.8E+06 1-131 1.0E+07 2.4E+l0 2.5E+09 4.8E+l l 5.8E+ll 1.6E+07 1-133 l.5E+06 4.0E+08 6.0E+Ol 4.4E+09 5.3E+09 3.8E+06 Cs-134 7.9E+09 2.5E+l0 l.1E+09 5.0E+IO l.5E+ll l.1E+06 Cs-136 1.7E+08 2.2E+08 4.2E+07 5.1E+09 l.5E+l0 1.9E+05 Cs-137 1.2E+l0 2.5E+l0 1.0E+09 4.5E+10 1.4E+ll 9.0E+05 Ba-140 2.3E+07 2.7E+08 5.2E+07 2.1E+08 2.6E+07 2.0E+06 Ce-141 1.5E+07 5.3E+08 3.0E+07 8.3E+07 l.OE+07 6.1E+05 Ce-144 7.9E+07 l.3E+10 3.6E+08 7.3E+08 8.7E+07 l.3E+07 Units for all except inhalation pathway are m2 mr sec / yr µ,Ci, inhalation pathway units are mr m3 / yr µ,Ci.

Uap Values to be Used For the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables and grain (kg/yr) 520 630 520 Leafy vegetables (kg/yr) 26 42 64 Milk (L/yr) 330 330 400 310 Meat and poultry (kg/yr) 41 65 110 Fish (kg/yr) 6.9 16 21 Drinking water (L/yr) 330 510 510 730 Shoreline recreation (hr/yr) 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table E-5 of Reg. Guide 1.109.

Information.1 PMP-6010-0SD-001 I

Rev. 26 OFF-SITE DOSE CALCULATION MANUAL Element H

C Na p

Cr Mn Fe Co Ni Cu Zn Br Rb Sr y

Zr Nb Mo Tc Ru Rh Te I

Cs Ba La Ce Pr Nd w

Np Dose Factors for Various Pathways B;p Factors for Aquatic Foods pCi I/ kg pCi Fish Invertebrate 9.0E-1 9.0E-1 4.6E3 9.1E3 l.OE2 2.0E2 l.OE5 2.0E4 2.0E2 2.0E3 4.0E2 9.0E4 l.OE2 3.2E3 5.0El 2.0E2 l.OE2 l.OE2 5.0El 4.0E2 2.0E3 1.0E4 4.2E2 3.3E2 2.0E3 l.OE3 3.0El 1.0E2 2.5El l.OE3 3.3EO 6.7EO 3.0E4 1.0E2 l.OEl l.OEl 1.5El 5.0EO l.OEl 3.0E2 l.OEl 3.0E2 4.0E2 6.1E3 1.5El

• 5.0EO 2.0E3 l.OE3 4.0EO 2.0E2 2.5El 1.0E3 l.OEO l.OE3 2.5El l.OE3 2.5El 1.0E3 l.2E3 l.OEl 1.0El 4.0E2 Table A-1 of Reg. Guide 1.109.

Page 51 of 98 Pages:

50 - 53

Information PMP-6010-0SD-001 I

Rev. 26 Page 52 of 98 OFF-SITE DOSE CALCULATION MANUAL.1 Dose Factors for Various Pathways Pages:

50 - 53 Daipj External Dose Factors for Standing on Contaminated Ground mrem m2 / hr pCi Radionuclide Total Body Skin H-3 0

0 C-14 0

0 Na-24 2.5E-8 2.9E-8 P-32 0

0 Cr-51 2.2E-10 2.6E-10 Mn-54 5.8E-9 6.8E-9 Mn-56 1.lE-8 1.3E-8 Fe-55 0

0 Fe-59 8.0E-9 9.4E-9 Co-58 7.0E-9 8.2E-9 Co-60 l.7E-8 2.0E-8 Ni-63 0

0 Ni-65 3.7E-9 4.3E-9 Cu-64 l.5E-9 1.7E-9 Zn-65

'4.0E-9 4.6E-9 Zn-69 0

0 Br-83 6.4E-11 9.3E-11 Br-84 1.2E-8 1.4E-8 Br-85 0

0 Rb-86 6.3E-10 7.2E-10 Rb-88 3.5E-9 4.0E-9 Rb-89 1.5E..:8 1.8E-8 Sr-89 5.6E-13 6.5E-13 Sr-91 7.lE-9 8.3E-9 Sr-92 9.0E-9 1.0E-8 Y-90 2.2E-12 2.6E-12 Y-91m 3.8E-9 4.4E-9 Y-91 2.4E-ll 2.7E-11 Y-92 l.6E-9 1.9E-9 Y-93 5.7E-10 7.SE-10 Zr-95 5.0E-9 5.8E-9 Zr-97 5.5E-9 6.4E-9 Nb-95 5.lE-9 6.0E-9 Mo-99 l.9E-9 2.2E-9 Tc-99m 9.6E-10 1.lE-9 Tc-101 2.7E-9 3.0E-9 Ru-103 3.6E-9 4.2E-9 Ru-105 4.5E-9 5.lE-9 Ru-106 l.5E-9 l.8E-9 Ag-llOm 1.8E-8 2.lE-8 Te-125m 3.5E-11 4.SE-11

Information PMP-6010-0SD-001 I

Rev. 26 Page 53 of 98 OFF-SITE DOSE CALCULATION MANUAL.1 Dose Factors for Various Pathways Pages:

50 - 53 Radionuclide Total Body Skin Te-127m l.lE-12 l.3E-12 Te-127 l.OE-11 l.lE-11 Te-129m 7.7E-10 9.0E-10 Te-129 7.lE-10 8.4E-10 Te-131m 8.4E-9 9.9E-9 Te-131 2.2E-9 2.6E-6 Te-132 l.7E-9 2.0E-9 I-130 l.4E-8 l.7E-8 I-131 2.8E-9 3.4E-9 I-132 l.7E-8 2.0E-8 I-133 3.7E-9 4.SE-9 I-134 l.6E-8 l.9E-8 I-135 l.2E-8 l.4E-8 Cs-134 l.2E-8 1.4E-8 Cs-136 1.5E-8 l.7E-8 Cs-137 4.2E-9 4.9E-9 Cs-138 2.lE-8 2.4E-8 Ba-139 2.4E-9 2.7E-9 Ba-140 2.lE-9 2.4E-9 Ba-141 4.3E-9 4.9E-9 Ba-142 7.9E-9 9.0E-9 La-140 l.SE-8 1.7E-8 La-142 1.SE-8 l.8E-8 Ce-141 5.SE-10 6.2E-10 Ce-143 2.2E-9 2.SE-9 Ce-144 3.2E-10 3.7E-10 Pr-143 0

0 Pr-144 2.0E-10 2.3E-10 Nd-147 1.0E-9 l.2E-9 W-187 3.lE-9 3.6E-9 Np-239 9.SE-10

1. lE-9 Table E-6 of Reg. Guide 1.109.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 54 of 98 OFF-SITE DOSE CALCULATION MANUAL.2 Radioactive Liquid Effluent Monitoring Instruments Pages:

54-56 INSTRUMENT Minimum Applicability Action

1.

2.

3.

4.

Channels Operablea Gross Radioactivity Monitors Providing Automatic Release Termination

a. Liquid Radwaste (1)#

At times of release 1

Effluent Line (RRS-1001)

b. Steam Generator (1)#

At times of release**

2 Blowdown Line (R-19, DRS 3/4100 +)

C. Steam Generator (1)#

At times of release 2

Blowdown Treatment Effluent (R-24, DRS 3/4200 +)

d. Mirion Liquid Radwaste (1)#

At times of release 1

Effluent Line (RRS-1001-A, RRS-1001-B)

e. Mirion Steam Generator (1)#

At times of release**

2 Blowdown Line (DRA-300)

f.

Mirion Steam Generator (1)#

At times of release 2

Blowdown Treatment Effluent (DRA-353)

Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Service Water (1) per At all times 3

System Effluent Line (R-20, R-28) train

b. Mirion Service Water (1) per At all times 3

System Effluent Line (Unit 1:WRA-713, train WRA-717) and (Unit 2: WRA-714, WRA-718)

Continuous Composite Sampler Flow Monitor

a. Turbine Building Sump (1)

At all times 3

Effluent Line Flow Rate Measurement Devices

a. Liquid Radwaste Line (1)

At times of release 4

(RFI-285)

b. Discharge Pipes*

(1)

At all times NA C. Steam Generator Blowdown (1)

At times of release 4

Treatment Effluent (DFl-352)

d. Individual Steam Generator sample flow (1) per At times of release 5

to Blowdown radiation monitors alarm generator (DFA-310, 320, 330 and 340)

Pump curves and valve settings may be utilized to estimate flow; in such cases, Action Statement 4 is not applicable. This is primarily in reference to start up flash tank flow.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 55 of 98 OFF-SITE DOSE CALCULATION MANUAL.2 Radioactive Liquid Effluent Monitoring Instruments Pages:

54-56 OPERABILITY ofRRS-1001 includes OPERABILITY of sample flow switch RFS-1010, which is an attendant instrument as defined in Technical Specification section 1.1, under the term Operable - Operability. This item is also applicable for all Eberline and Mirion liquid monitors (and their respective flow switches) listed here.

Since these monitors can be used for either batch or continuous release the appropriate action statement of 1 or 2 should apply (that is, Action 1 if a steam generator drain is being performed in lieu of Action 2). It is possible, due to the steam generator sampling system lineup, that BOTH action statements are actually entered. This would be the case when sampling for steam generator draining requires duplicate samples while the sample system is lined up to discharge to the operating units blowdown system. In this case the steam generator drain samples can fulfill the sample requirement for Action 2 also. Action 2 would be exited when sampling was terminated.

+

. Westinghouse I and Eberline (DRS) monitors are being replaced by Mirion monitors. Either monitor can fulfill the operability requirement. Ensure surveillances are current for operability of the instrumentation prior to using it to satisfy applicability requirement.

a IF an RMS monitor is inoperable solely as the result of the loss of its control room alarm annunciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:

1.

Collect grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2.

Collect local monitor readings at a frequency equal to or greater than (more frequently than) the action frequency.

IF the RMS monitor is inoperable for.reasons other than the loss of control room annunciation, THEN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

Action 1 Action 2 TABLE NOTATION With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Step 3.2.3a and;

2. At least two technically qualified members of the Facility Staff independently verify the discharge valving. Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 µCi/gram:

1. At least once per shift when the specific activity of the secondary coolant is > 0.01 µCi/gram DOSE EQUIVALENT 1-131.

2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is s 0.01 µCi/gram DOSE EQUIVALENT 1-131_.

After 30 days, IF the channels are not OPERABLE, THEN continue releases with required grab samples provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 56 of 98 OFF-SITE DOSE CALCULATION MANUAL.2 Radioactive Liquid Effluent Monitoring Instruments Pages:

54-56 Action 3 Action 4 Action 5 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per shift, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 µCi/ml. Since the Westinghouse ESW monitors (R-20 and R-

28) and Mirion ESW monitors (WRA-713/717 U1 and WRA-714/718 U2) are only used for post LOCA leak detection and have no auto trip function associated with them, grab samples are only needed if the Containment Spray Heat Exchanger is in service. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is verified to be within the required band at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report. IF the flow cannot be obtained within the desired band, THEN declare the radiation monitor inoperable and enter the appropriate actions statement, Action 2.

Compensatory actions are governed by PMP--4030-EIS-001, Event-Initiated Surveillance Testing

Information PMP-6010-0SD-001 I

Rev. 26 Page 57 of 98 OFF-SITE DOSE CALCULATION MANUAL.3 Radioactive Liquid Effluent Monitoring Pages:

Instrumentation Surveillance Requirements 57 - 58 Instrument CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION OPERATIONAL TEST

1. Gross Radioactivity Monitors Providing Automatic Release Termination

a. Liquid Radwaste D*

p B(3)

Q(5)

Effluent Line (RRS-1001)

b. Mirion Liquid D*

p B(3)

Q(5)

Radwaste Effluent Line (RRS-1001-A, RRS-1001-B)

C. Steam Generator D*

M B(3)

Q(l)

Blowdown Effluent Line

d. Steam Generator D*

M B(3)

Q(l)

Blowdown Treatment Effluent Line

2.

Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Service Water D

M B(3)

Q(2)

System Effluent Line

3.

Continuous Composite Samplers

a. Turbine Building D*

NIA NIA NIA Sump Effluent Line

4.

Flow Rate Measurement Devices

a. Liquid Radwaste D(4)*

NIA B

Q Effluent

b. Steam Generator D(4)*

NIA NIA NIA Blowdown Treatment Line

• During releases via this pathway. This is applicable to all surveillances for the appropriate monitor.

Information PMP-6010-0SD-001 I

Rev. 26 Page 58 of 98 OFF-SITE DOSE CALCULATION MANUAL.3 Radioactive Liquid Effluent Monitoring Pages:

Instrumentation Surveillance Requirements 57 - 58 TABLE NOTATION

1.

Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.*

3. Instrument indicates a downscale failure.*

4. Instrument control not set in operating mode.*

5. Loss of sample flow (Non-Mirion monitors only). *

2.

Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operating mode.

3.

Perform the initial CHANNEL CALIBRATION using one or more sources with traceability back to the National Institute of Standards and Technology (NIST). These sources permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.

4.

Verify indication of flow during periods ofrelease with the CHANNEL CHECK. Perform the CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made.

5.

Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.**

3. Instrument indicates a downscale failure.**

4. Instrument control not set in operating mode.*

5. Loss of sample flow (Non-Mirion monitors only).

Instrument indicates, but does not provide for automatic isolation Instrument indicates, but does not necessarily cause automatic isolation. No credit is taken for the automatic isolation on such occurrences.

Operations currently performs the routine channel checks and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests. Chemistry performs the channel check on the continuous composite sampler.

These responsibilities are subject to change without revision to this document.

Information PMP-6010-0SD-001 I

Rev. 26 Page 59 of 98 OFF-SITE DOSE CALCULATION MANUAL.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:

59-62 Instrument (Instrument #)

Operable1 Minimum Action Channels Action

1.

Condenser Evacuation System

a.

Noble Gas Activity (1) 6 Monitor (SRA-1905/2905)

b.

Flow Rate Monitor (SFR-401 and 1/2-MR-(1) 5 054) OR (SFR-401 and SRA-1910/2910)

OR (SFR-402 and l/2-MR-054)

C.

Mirion Noble Gas Activity (1) 6 Monitor (SRA-1905-N1905-B and SRA-2905-A/2905-B)

d.

Mirion Flow Rate Monitor (SFR-401 and (1) 5 PPC/RadServe SJAE display point) OR (SFR-401 and SRA-1910/2910 local display)

OR (SFR-402 and Ul/U2 PPC/RadServe SJAE display point)

2.

Unit Vent. Auxiliary Building Ventilation System

a.

Noble Gas Activity (1) 6 Monitor (VRS-1505/2505)

b.

Iodine Sampler (1) 8 Cartridge for VRA-1503/2503 C.

Particulate Sampler Filter (1) 8 for VRA-1501/2501

d.

Effluent System Flow Rate (1) 5 Measuring Device (VFR-315 and 1/2-MR-054) OR (VFR-315 and VFR-1510/2510)

e.

Sampler Flow Rate (1) 5 Measuring Device (VFS-1521/2521)

f.

Mirion Noble Gas Activity (1) 6 Monitor (VRS-1505-A/1505-B and VRS-2505-A/2505-B)

g.

Mirion Effluent System Flow Rate (1) 5 Measuring Device (VFR-315 and Ul/U2 PPC/RadServe V AB display point) OR (VFR-315 and VFR-1510/2510 local display)

h.

Sampler Flow Rate (1) 5 Measuring Device (Ul/U2 PPC/RadServe V AB display point) OR (VRS-1500/2500 local display)

3.

Containment Purge and Containment Pressure Relief (Vent) **

a.

Containment Noble Gas Activity Monitor (1)

• • • • 2, 3 7

ERS-1305/1405 (ERS-2305/2405)

b.

Containment Particulate Sampler Filter (1) 10 ERS-1301/1401 (ERS-2301/2401)

Information PMP-6010-0SD-001 I

Rev. 26 Page 60 of 98 OFF-SITE DOSE CALCULATION MANUAL.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:

59-62 Instrument (Instrument #)

Operable1 Minimum Action

4.

5.

Channels Action Waste Gas Holdup System and CVCS HUT (Batch releases)**

a.

Noble Gas Activity (1)

• • • • 4 9

Alarm and Termination of Waste Gas Releases (VRS-1505/2505)

b.

Mirion Noble Gas Activity (1)

• • • • 4 9

Alarm and Termination of Waste Gas Releases (VRS-1505-A/1505-B and VRS-2505-A/2505-B)

Gland Seal Exhaust

a.

Noble Gas Activity (1) 6 Monitor (SRA-1805/2805)

b.

Flow Rate Monitor (SFR-201 and 1/2-MR-(1) 5

54) OR (SFR-201 and SFR-1810/2810)

C.

Mirion Flow Rate Monitor (SFR-201 and (1) 5 Ul/U2 PPC/RadServe GSLO display point)

OR (SFR-201 and SFR-1810/2810 local display)

At all times Containment Purge and other identified gaseous batch releases can be released utilizing the same double sampling compensatory action requirements of action 9 identified here even if there is no termination function associated with it like that associated with the two specific tank types listed here.

• • • • During releases via this pathway TABLE NOTATIONS

1. IF an RMS monitor is INOPERABLE solely as the result of the loss of its control room alarm annunciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:

l.

Take grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2.

Take local monitor readings at a frequency equal to or greater than (more frequently than) the action frequency.

IF the RMS monitor is inoperable for reasons other than the loss of control room annunciation, THEN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

With the Mirion RMS Upgrades, it is intended that an OPERABLE instrument/channel listed in the ODCM has both an operable transmitter and an operable display point, which may be local to the skid or on the PPC/RadServe system. This is in addition to control room annunciation function, if applicable.

Information PMP-6010-0SD-001 I

Rev. 26 Page 61 of 98 OFF-SITE DOSE CALCULATION MANUAL.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:

59-62

2. Consider releases as occurring "via this pathway" under the following conditions:

The Containment Purge System is in operation and Containment Operability is applicable,

-OR-The Containment Purge System is in operation and the 'Clean-up' batch release of the Containment air volume has not been fully completed.

IF neither of the above are applicable AND the unit is in Mode 5 or 6, THEN the containment purge system is acting as a ventilation system (an extension of the Auxiliary Building) and is covered by Item 2 of this Attachment. This is called 'Ventilation Mode'.

'Ventilate Mode' cannot be entered without performing a Clean-up batch release.

-OR-A Containment Pressure Relief (CPR) is being performed.

Once the 'Clean-up' batch release has been completed and 'Ventilation' mode of Purge has commenced -

resultant return to 'Clean-up' mode can be made with no additional sampling requirements or paperwork - so long as either ERS-1305/2305 OR ERS-1405/2405 are operable. Containment particulate channels are not needed once the RCS has entered Mode 5 per Technical Specification 3.4.15.

3. *For purge (including pressure relief) purposes only. Reference TS 3.3.6, Containment Purge Supply and Exhaust System Isolation Instrumentation and 3.4.15, RCS Leakage Detection Instrumentation for additional information.

4. For waste gas releases only, see Item 2 (Unit Vent, Auxiliary Building Ventilation System) for additional requirements.

ACTIONS

5. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with estimation of the flow rate once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

6. With the number of channels OPERABLE less required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

7. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, immediately suspend PURGING or VENTING (CPR) of radioactive effluents via this pathway.

8.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples required for weekly Iodine & Particulates analysis are continuously collected with auxiliary sampling equipment as required in Attachment 3.7, Radioactive Gaseous Waste Sampling and Analysis Program. After 30 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

Sampling evolutions are not an interruption of a continuous release or sampling period.

Information PMP-6010-0SD-001 I

Rev. 26 Page 62 of 98 OFF-SITE DOSE CALCULATION MANUAL.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:

59-62

9. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed and,

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineups; otherwise, suspend release of radioactive effluents via this pathway.

After 14 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report

10. Technical Specification 3.4.15, RCS Leakage Detection System Instrumentation.

This Space Intentionally Blank Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing.

Information PMP-6010-0SD-001 I

Rev. 26 Page 63 of 98 OFF-SITE DOSE CALCULATION MANUAL.5 Radioactive Gaseous Effluent Monitoring Pages:

Instrumentation Surveillance Requirements 63 - 65 Instrument CHANNEL SOURCE I

CHANNEL CHANNEL OPERATIONAL CHECK CHECK CALIBRATION TEST

1. Condenser Evacuation Alarm Only System

a. Noble Gas Activity Monitor D**

M B(2)

Q(l)

(SRA-1905/2905)

b. System Effluent Flow Rate D**

NA B

Q (SFR-401, SFR-402, MR-054, SRA-1910/2910)

c. Mirion Noble Gas Activity D**

M B(2)

Q(l)

Monitor (SRA-1905-A/ 1905-B, SRA-2905-A/ 2905-B)

d. Mirion System Effluent Flow D**

NA B

Q Rate (SFR-401, SFR-402, Ul/U2 PPC/RadServe SJAE display point, SRA-1910/2910)

2. Auxiliary Building Unit Alarm Only Ventilation System

a. Noble Gas Activity Monitor D*

M B(2)

Q(l)

(VRS-1505/2505)

b. Iodine Sampler W*

NA NA NA (For VRA-1503/2503)

C. Particulate Sampler W*

NA NA NA (For VRA-1501/2501)

d. System Effluent Flow Rate D*

NA B

Q Measurement Device (VFR-315, MR-054, VRS-1510/2510)

e. Sampler Flow Rate D*

NIA B

Q Measuring Device (VFS-1521/2521)

f. Mirion Noble Gas Activity D*

M B(2)

Q(l)

Monitor (VRS-1505-A/ 1505-B and VRS-2505-N 2505-B)

g. Mirion System Effluent Flow D*

NA B

Q Rate Measurement Device (VFR-315, Ul/U2 PPC/RadServe V AB display point, VRS-1510/2510)

h. Mirion Sampler Flow Rate D*

NIA B

Q Measuring Device (Ul/U2 PPC/RadServe V AB display point or local display)

Information PMP-6010-0SD-001 I

Rev. 26 Page 64 of 98 OFF-SITE DOSE CALCULATION MANUAL.5 Radioactive Gaseous Effluent Monitoring Pages:

Instrumentation Surveillance Requirements 63 - 65

3. Containment Purge System and Alarm and Trip Containment Pressure Relief

a. Containment Noble Gas s

p B(2)

Q Activity Monitor (ERS-13/1405 and ERS-23/2405)

b. Containment Particulate s

NA B

Q Sampler (ERS-13/1401 and ERS-23/2401)

4. Waste Gas Holdup System Alarm and Trip Including eves HUT

a. Noble Gas Activity Monitor p

p B(2)

Q(3)

Providing Alarm and Termination (VRS-1505/2505)

b. Mirion Noble Gas Activity p

p B(2)

Q(3)

Monitor Providing Alarm and Termination (VRS-1505-A/1505-B and VRS-2505-A/2505-B)

5. Gland Seal Exhaust Alarm Only

a. Noble Gas Activity D**

M B(2)

Q(l)

(SRA-1805/2805)

b. System Effluent Flow Rate D**

NA B

Q (SFR-201, MR-054, SRA-1810/2810)

C. System Effluent Flow Rate D**

NA B

Q (SFR-201, Ul/U2 PPC/RadServe V AB display point, SRA-1810/2810)

• At all times

• • During releases via this pathway. This is applicable to all surveillances for the appropriate monitor.

TABLE NOTATIONS

1.

Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

2.

Perform the initial CHANNEL CALIBRATION using one or more sources with traceability back to the NIST. These sources permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.

Information PMP-6010-0SD-001 I

Rev. 26 Page 65 of 98 OFF-SITE DOSE CALCULATION MANUAL.5 Radioactive Gaseous Effluent Monitoring Pages:

Instrumentation Surveillance Requirements 63 - 65

3.

Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

Circuit failure.*

3.

Instrument indicates a downscale failure.*

4.

Instrument controls not set in operate mode.*

• Instrument indicates, but does not provide automatic isolation.

Operations currently performs the routine channel checks, and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests.

These responsibilities are subject to change without revision to this document.

Rest of this page intentionally blank

Information PMP-6010-0SD-001 I

Rev. 26 I Page 66 of 98 OFF-SITE DOSE CALCULATION MANUAL.6 Radioactive Liquid Waste Sampling and Analysis Program Pages:

66-67

[Ref 5 2 lt]

LIQUID SAMPLING MINIMUM TYPE OF LOWER RELEASE FREQUENCY ANALYSIS ACTIVITY LIMIT OF TYPE FREQUENCY ANALYSIS DETECTION (LLD)

(µCi/ml) a A. Batch Waste p

p Principal 5x10-7 Release Tanks c Each Batch Each Batch Gamma Emitters e I-131 ix10-6 p

p Dissolved and Entrained Gases Each Batch Each Batch (Gamma lxl0-5 Emitters) p M

H-3 lx10-5 Each Batch Compositeb Gross Alpha lx10-7 p

Q Sr-89, Sr-90 5x10-s Each Batch Compositeb Fe-55 lxl0-6 B. Plant w

Principal Continuous Daily Compositeb Gamma 5x10-7 Releases* d Emitters 0

I-131 lxl0-6 M

M Dissolved and Grab Sample Entrained Gases lxlQ-5 (Gamma Emitters)

M H-3 lxl0-5 Daily Compositeb Gross Alpha lx10-7 Q

Sr-89, Sr-90 5xl0-8 Daily Compositeb Fe-55 lxl0-6

• During releases via this pathway This table provides the minimum requirements for the liquid sampling program. If additional sampling is performed then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification.

Examples of these samples are the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> secondary coolant activity and Monitor Tank tritium samples.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 67 of 98 OFF-SITE DOSE CALCULATION MANUAL.6 Radioactive Liquid Waste Sampling and Analysis Program Pages:

66-67 TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, isolate and ensure thorough mixing (recirculate, sparge, etc) for each batch. Examples of these are Monitor Tank and Stearn Generator Drains. Before a batch is released the tank is sampled and analyzed to determine that it can be released without exceeding federal standards.

d. A continuous release is the discharge of liquid of a non-discrete volume; e.g. from a volume of system that has an input flow during the continuous release. This type of release includes the Turbine Room Sump, Steam Generator Blowdown and the Steam Generator Sampling System.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144.

This list does not mean that only these nuclides are to be detected and reported. Identify and report other peaks, which are measurable and identifiable, together with the above nuclides.

Information PMP-6010-0SD-001 I

Rev. 26 Page 68 of 98 OFF-SITEDOSE CALCULATION MANUAL.7 Radioactive Gaseous Waste Sampling and Pages:

Analysis Program 68 - 69 Gaseous Release Type Frequency Minimum Type of Lower Limit Analysis Activity of Detection Frequency Analysis

(µCi/cc)*

a. Waste Gas Storage p

p Principal Gamma Tanks and eves HUTs Each Tank Each Tank Emittersd 1 X 104 Grab Sample H-3 1 X 10-6

b. Containment Purge p

p Principal Gamma Each Purge Each Purge Emitters d 1 X 104 Grab Sample CPR (vent)**

Twice per Twice per Month Month H-3 1 X 10-6 C. Condenser Evacuation WorM M

Principal Gamma System Grab Sample Particulate Sample Emittersd 1 X 10-11 Gland Seal Exhaust* ;

M H-3 1 X 10-6 wg Principle Gamma 1 X 104 Noble Gas Emitters d M

1-131 Iodine Adsorbing 1 X 10-12 Media Continuous wg Noble Gases Noble Gas Monitor 1 X 10-6

d. Auxiliary Building Unit Continuous c Wb 1-131 Vent*

Iodine Adsorbing 1 X 10-12 Media Continuous c wb Principal Gamma Particulate Sample Emitters ct 1 X 10-ll Continuous c M

Gross Alpha Composite Particulate 1 X 10-11 Sample w

Wh H-3 Grab Sample H-3 Sample 1 X 10-6 Wgi Principle Gamma 1 X 104 Noble Gas Emitters ct Continuous c Q

Sr-89, Sr-90 Composite Particulate 1 X 10-ll Sample Continuous c Noble Gas Monitor Noble Gases 1 X 10-6

e. Incinerated Oil

• p p

Principal Gamma Each Batch r Each Batch r Emitters ct 5 X 10-7

• Durmg releases via this pathway

• • Only a twice per month sampling program for containment noble gases and HJ is required This table provides the minimum requirements for the gaseous sampling program.

If additional sampling is performed then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification. Examples of these samples are verification or compensatory action sample results.

Information PMP-6010-0SD-001 I

Rev. 26 Page 69 of 98 OFF-SITE DOSE CALCULATION MANUAL.7 Radioactive Gaseous Waste Sampling and Pages:

Analysis Program 68-69 TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP

b. Change samples at least once per 7 days and complete analyses within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.

Perform analyses at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or THERMAL POWER change greater than 15% per hour of RATED THERMAL POWER. WHEN samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, THEN the corresponding LLDs may be increased by a factor of

10. This requirement does not apply IF (1) analysis shows that DOSEQ 1131 concentration in the RCS has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. IF the daily sample requirement has been entered, THEN it can be exited early once both the radiation monitor reading and the RCS DOSEQ 1131 levels have returned to within the factor of 3 of the pre-event 'normal'.[Ref. 5.2. lz]

c. Know the ratio of the sample flow rate to the sampled stream flow rate for the time period covered by each dose or dose rate calculation made in accordance with steps 3.2.4a, 3.2.4b, and 3.2.4c of this document.

Sampling evolutions or momentary interruptions to maintain sampling capability are not an interruption of a continuous release or sampling period.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Identify and report other peaks, which are measurable and identifiable, together with the above nuclides.

e. Releases from incinerated oil are discharged through the Auxiliary Boiler System. Account for releases based on pre-release grab sample data.

f. Collect samples of waste oil to be incinerated from the container in which the waste oil is stored (example: waste oil storage tanks, 55 gal. drums) prior to transfer to the Auxiliary Boiler System.

Ensure samples are representative of container contents.

. g. Obtain and analyze a gas marinelli grab sample weekly for noble gases effluent quantification.

h. Take tritium grab samples at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.

i. Grab sampling of the Gland Seal Exhaust pathway need not be performed if the RMS low range channel (SRA-1805/2805) (or Mirian normal range channel) readings are less than lE-6 µC/cc. Attach the RMS daily averages in lieu of sampling. This is based on operating experience indicating no activity is detected in the Gland Seal Exhaust below this value. Compensatory sampling for out of service monitor is still required in the event 1805/2805 is inoperable.

j. Sampling and analysis shall also be performed following shutdown, startup or THERMAL POWER change exceeding 15 % of RA TED THERMAL POWER within a one hour period. This noble gas sample shall be performed within four hours of the event. Evaluation of the sample results, based on previous samples, will be performed to determine if any further sampling is necessary.

Information PMP-6010-0SD-001 I

Rev. 26 Page 70 of 98 OFF-SITE DOSE CALCULATION MANUAL.8 Multiple Release Point Factors for Release Points Page:

70 - 71 Liquid Factors Monitor Description Monitor Number MRP#

U 1 SG Blowdown l-DRA-300, l-DRA-353, 1R19/24, 0.35 DRS 3100/3200*

U 2 SG Blowdown 2-DRA-300, 2-DRA-353, 2R19/24, 0.35 DRS 4100/4200*

U 1 & 2 Liquid Waste Discharge RRS-1001-A, RRS-1001-B, 0.30 RRS-1000 ( c)

Sources of radioactivity released from the Turbine Room Sump (TRS) typically originate from the secondary cycle which is already being monitored by instrumentation that utilizes multiple release point (MRP) factors. The MRP is an administrative value that is used to assist with maintaining releases ALARA. The TRS has no actual radiation monitor, but utilizes an automatic compositor for monitoring what has been released. The batch release path, through RRS-1000 (RRS-1001-A/B), is the predominant release path by several magnitudes. Tritium is the predominant radionuclide released from the site and the radiation monitors do not respond to this low energy beta emitter. Based on this information and the large degree of conservatism built into the radiation monitor setpoint methodology it does not appear to warrant further reduction for the TRS release path since its source is predominantly the secondary cycle which is adequately covered by this factor.

Gaseous Factors Monitor Description Monitor Number Flow Rate ( cfm)

MRP#

Unit 1 Unit Vent VRS-1500 186,600 0.54 Gland Seal Vent SRA-1800 1,260 0.00363 Steam Jet Air Ejector SRA-1900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 192,996 Unit2 Unit Vent VRS-2500 143,400 0.41 Gland Seal Vent SRA-2800 5,508 (a) 0.02 Steam Jet Air Ejector SRA-2900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 154,044

a b

C Information PMP-6010-0SD-001 I

Rev. 26 Page 71 of 98 OFF-SITE DOSE CALCULATION MANUAL.8 Multiple Release Point Factors for Release Points Page:

70 - 71 Either Mirion monitors (DRA) or Westinghouse R-19, 24/ Eberline monitors (DRS) can be used for blowdown monitoring as the Mirion monitors are replacing both the Eberline monitors (DRS) and the Westinghouse I monitors.

Nominal Values Two release points of2,754 cfm each are totaled for this value.

This is the total design maximum of the Start Up Air Ejectors. This is a conservative value for unit 1.

Either the Mirion (RRS-1001-A/B) or the current RRS-1000 monitor may be used for liquid waste discharges as the Mirion monitors replace RRS-1000 monitor.

Rest of page is blank by intent

Information PMP-6010-0SD-001 I

Rev. 26 OFF-SITE DOSE CALCULATION MANUAL.9 SOURCES Dirty Wastes:

Floor Drains, Decontamination Rinse Solutions, Chemical Drain Tank.Be.

Clean Wastes:

Equipment Drains, Pump Seal

Leakoffs, Containment Fan Cooler Condensate,Bc.

eves Boric acid Evaporator Packages, North and South Steam Generator Slowdown and Slowdown Treatment System (Potential)

Essential Service Water System (Potential)

Turbine Room Sump Unit 1 and 2 (Potential)

StationOrain(Dirty)

Sump Tank Steam Generator Circulating Waler lntakePf es Turbine Room Sump Ef.571'Sump Liquid Effluent Release Systems SYSTBvlS pump

! Strained--------..~

__J -~--+

Normal SIG Pum Slowdown Heat Exchan er Start UpS/G

,,~~~:~on I Screen House

~

I sample Point GP

~ Containment Spray Heat Exchan ers Page 72 of 98 Page:

72 Circulating Water Discharge Circulating Water Discharge Circulating Water.

Discharge RB.EASE FOINTS Lake Michigan Lake Michigan

Information PMP-6010-0SD-001 I

Rev. 26 OFF-SITE DOSE CALCULATION MANUAL 1.10 Plant Liquid Effluent Parameters SYSTEM I

Waste Disposal System

+ Chemical Drain Tank

+ Laundry & Hot Shower Tanks

+ Monitor Tanks

+ Waste Holdup Tanks

+ Waste Evaporators

+ Waste Evaporator Condensate Tanks II Steam Generator Blowdown and Blowdown Treatment Systems

+ Start-up Flash Tank (Vented)#

+ Normal Flash Tank (Not Vented)

+ Blowdown Treatment System III Essential Service Water System

+ Water Pumps

+ Containment Spray Heat Exchanger Outlet IV Circulating Water Pumps I Unit I Unit 2 Nominal Values COMPONENTS CAPACITY TANKS I PUMPS (EACH) 1 1

600 GAL.

2 1

600 GAL.

4 2

21,600 GAL.

2 25,000 GAL.

3 2

2 6,450 GAL 1

1,800 GAL.

1 525 GAL.

1 4

4 3

4 Page 73 of 98 Page:

73 FLOW RATE (EACH)*

20 GPM 20 GPM 150 GPM 30 GPM 150 GPM 580 GPM 100 GPM 60 GPM 10,000 GPM 3,300 GPM 230,000 GPM 230,000 GPM The 580 gpm value is calculated from the Estimated Steam Generator Blowdown Flow vs. DRV Valve Position letter prepared by M. J. O'Keefe, dated 9/27/93. This is 830 gpm times the 70% that remains as liquid while the other 30 % flashes to steam and exhausts out the flash tank vent.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 74 of 98 OFF-SITE DOSE CALCULATION MANUAL Volumetric Detection Efficiencies for Principle Gamma Pages:.11 Emitting Radionuclides for Eberline and Mirian Liquid 74-75 Monitors This includes the following monitors: RRS-1000, DRS 3100, DRS 3200, DRS 4100, and DRS 4200.

[Ref. 5.2.lq]

NUCLIDE EFFICIENCY (cpm/uCi/cc) 1-131 3.78 E7 Cs-137 3.00 E7 Cs-134 7.93 E7 Co-60 5.75 E7 Co-58 4.58 E7 Cr-51 3.60 E6 Mn-54 3.30 E7 Zn-65 1.58 E7 Ag-110M 9.93 E7 Ba-133 4.85 E7 Ba-140 1.92 E7 Cd-109 9.58 ES Ce-139 3.28 E7 Ce-141 1.92 ES Ce-144 4.83 E6 Co-57 3.80 E7 Cs-136 1.07 ES Fe-59 2.83 E7 Sb-124 5.93 E7 1-133 3.40 E7 1-134 7.23 E7 1-135 3.95 E7 Mo-99 8.68 E6 Na-24 4.45 E7 Nb-95 3.28 E7 Nb-97 3.50 E7 Rb-89 5.00 E7 Ru-103 3.48 E7 Ru-106 1.23 E7 Sb-122 2.55 E7 Sb-125 3.15 E7 Sn-113 7.33 ES Sr-85 3.70 E7 Sr-89 2.88 E3 Sr-92 3.67 E7 Tc-99M 3.60 E7 Y-88 5.25 E7 Zr-95 3.38 E7 Zr-97 3.10 E7 Kr-85 1.56 ES Kr-85M 3.53 E7 Kr-88 4.10 E7 Xe-131M 8.15 ES Xe-133 7.78 E6 Xe-133M 5.75 E6 Xe-135 3.83 E7

Information PMP-6010-0SD-001 I

Rev. 26 I Page 75 of 98 OFF-SITE DOSE CALCULATION MANUAL Volumetric Detection Efficiencies for Principle Gamma Pages:.11 Emitting Radionuclides for Eberline and Mirion Liquid 74-75 Monitors Mirion RRS-lOOlA/B Detection Detection efficiency efficiency Nuclide

{ cps/ (Bq/m3)}

{cpm/( µCi/cc)}

Ag-108m 7.22E-04 1.60E+09 Ag-110m 8.45E-04 1.88E+09 Ba-137m 2.42E-04 5.37E+08 Ce-144 1.01 E-05 2.24E+07 Co-57 6.78E-05 1.51E+08 Co-58 3.38E-04 7.50E+08 Co-60 4.99E-04 1.11E+09 Cr-51 2.47E-05 5.48E+07 Cs-134 5.92E-04 1.31E+09 Cs-137 2.27E-04 5.04E+08 Fe-55 9.91 E-14 2.20E-01 Fe-59 2.62E-04 5.82E+08 1-131 2.50E-04 5.55E+08 1-133 2.71E-04 6.02E+08 ln-113m 1.71E-04 3.80E+08 Kr-85 1.15E-06 2.55E+06 Mn-54 2.67E-04 5.93E+08 Mo-99 1.53E-04 3.40E+08 Na-24 4.23E-04 9.39E+08 Nb-95 2.66E-04 5.91E+08 Pr-144 5.93E-06 1.32E+07 Sb-122 2.02E-04 4.48E+08 Sb-124 4.75E-04 1.05E+09 Sb-125 2.23E-04 4.95E+08 Sn-113 1.75E-04 3.89E+08 Sn-117m 1.19E-04 2.64E+08 Tc-99m 9.10E-05 2.02E+08 Xe-131m 2.84E-06 6.30E+06 Xe-133 1.32E-07 2.93E+05 Xe-133m 2.19E-05 4.86E+07 Xe-135 2.0BE-04 4.62E+08 Zn-65 1.33E-04 2.95E+08 Zr-95 2.66E-04 5.91E+08 Bq =Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µ,Ci/cc)

Information.12 "C

C:

, e PMP-6010-0SD-001 I Rev. 26 OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency for R-19, l/2-DRA-300, R-24, and l/2-DRA-353 Counting Efficiency Curve forR-19 Efficiency Factor= 4.2 E6 cpm/uCi/ml (Based on empirical data taken during pre-operational testing with Cs-137)

I

~ 1.00E+04 +-------------------------,,,""'------------------;

il

.Q

~

i 1.00E+03 4----------------,,,,,,.c__-------------------------l

~

(.J to 0

ill 0

0

~

lO 0

ill 0

0

'ST C')

0 0

ill ill 0

0 CC!

CC!

microcuries/ml N

0 ill 0

CC!

0 ill 0

CC!

0

t 0

0 Page 76 of 98 Pages:

76 -79

Information.12 PMP-6010-0SD-001 I. Rev. 26 I OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency for R-19, l/2-DRA-300, R-24, and l/2-DRA-353 Mirian 1/2-DRA-300 2rr Shield Detection Detection efficiency efficiency Nuclide

{cps/(Bq/m3)}

{cpm/( µCi/cc)}

Mn-54 3.99E-06 8.86E+06 Co-58 5.33E-06 1.18E+07 Co-60 7.46E-06 1.66E+07 Cs-137 3.72E-06 8.26E+06 1-131 4.68E-06 1.04E+07 1-132 1.20E-05 2.66E+07 1-133 4.45E-06 9.88E+06 I-134 1.22E-05 2.71E+07 l-135D 1.08E-05 2.40E+07 (based on actual pre-installation counting performed with an iodine source term)

Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc)

Page 77 of 98 Pages:

76-79 21r Shield= shielding encompasses the detector but not the sample piping per design criteria Mirion Detectors l/2-DRA-300 replace the R-19 and DRS-3100/4100 detectors

Information.12 (0

0 LU 0 q PMP-6010-0SD-001 I Rev. 26 OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency for R-19, l/2-DRA-300, R-24, and l/2-DRA-353 U')

c:,:>

w 0 q Counting Efficiency Curve for R-24 Efficiency Factor = 7.5E6 cpm/uCi/ml (Based on empirical data taken during pre-operational testing with Mn-54)

"<I" C')

N 0

0

~

LU LU 0

0 0

q q

q microcuries/ml 0

LU 0 q I

Page 78 of 98 Pages:

76-79 0

0 + w 0 q

Information.12 PMP-6010-0SD-001 I Rev. 26 I OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency for R-19, l/2-DRA-300, R-24, and l/2-DRA-353 Mirion l/2-DRA-353 2n: Shield Detection Detection efficiency efficiency Nuclide (cps/ (Bq/ mJll

{cpm/( µCi/cc)}

Mn-54 1.33E-05 2.95E+07 Co-58 1.74E-05 3.86E+07 Co-60 2.56E-05 5.q8E+07 Cs-137 1.13E-05 2.51E+07 1-131 l.13E-05 2.51E+07 1-132 3.69E-05 8.19E+07 1-133 l.30E-05 2.89E+07 1-134 3.62E-05 8.04E+07 l-135D 2.89E-05 6.42E+07 (based on actual pre-installation counting performed with an iodine source term)

Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc)

Page 79 of 98 Pages:

76-79 21r Shield= shielding encompasses the detector but not the sample piping per design criteria Mirion Detectors l/2-DRA-353 replace the R-24 and DRS-3200/4200 detectors

• Information.13 1.00E+07 1.00E+06 1.00E+05

-c C:

, e

]' 1.00E+04 u..

.a

~

0

.a 1.00E+03

a.

0 1.00E+02 1.00E+01 1.00E+OO c.o

~

0

~

PMP-6010-0SD-001 I Rev. 26 OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency for R-20, R-28, 1-WRA-713, 2-WRA-714, l-WRA-717, and LO

~

0

~

2-WRA-718 Counting Efficiency Curve for R-20 and R-28 Efficiency Factor= 4.3 E6 cpm/uCi/ml (Based on empirical data taken during pre--0perational testing with Co-58)

N 0

0

~

UJ UJ 0

0 0

~

~

~

microcuries/ml c5 UJ 0

~

I 0

'i?

UJ 0

0 Page 80 of 98 Pages:

80-82

Information PMP-6010-0SD-001 I Rev. 26 I Page 81 of 98 OFF-SITE DOSE CALCULATION MANUAL.13 Counting Efficiency for R-20, R-28, l-WRA-713, 2-WRA-714, l-WRA-717, and Pages:

Mirian Nuclide Am-241 Ba-137m Ba-139 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Cs-134 Cs-136 Cs-137 1-131 1-132 1-133 1-134 1-135D Kr-85 Kr-85m Kr-87 R-20 replacement 1-WRA713, 2-WRA-714 Detection Detection efficiency efficiency

{ cps/(Bq/m3)}

{cpm/( µCi/cc)}

4.81E-10 1.07E+03 2.79E-06 6.19E+06 8.02E-07 1.78E+06 1.31 E-06 2.91E+06 1.34E-06 2.97E+06 2.18E-06 4.84E+06 2.54E-07 5.64E+05 7.56E-11 1.68E+02 5.06E-11 1.12E+02 7.26E-06 1.61E+07 8.68E-06 1.93E+07 2.63E-06 5.84E+06 3.45E-06 7.66E+06 9.53E-06 2.12E+07 3.35E-06 7.44E+06 9.04E-06 2.01E+07 8.02E-06 1.78E+07 1.39E-08 3.09E+04 2.81E-06 6.24E+06 2.68E-b6 5.95E+06 2-WRA-718 Mirian 1-WRA713, 2-WRA-714 Detection Detection efficiency efficiency Nuclide

{cps/(Bq/m3)}

{cpm/( µCi/cc)}

Kr-88 4.04E-06 8.97E+06 La-140 6.SOE-06 1.44E+07 La-141 5.68E-08 1.26E+05 La-142 4.43E-06 9.83E+06 Mo-99 3.25E-06 7.22E+06 Nb-95 3.0BE-06 6.84E+06 Nd-147 7.07E-07 1.57E+06 Np-239 1.90E-06 4.22E+06 Pr-143 3.78E-14 8.39E-02 Pr-144 7.41 E-08 1.65E+05 Pu-238 6.62E-11 1.47E+02 Pu-239 4.97E-10 1.10E+03 Pu-240 6.93E-11 1.54E+02 Pu-241 1.18E-11 2.62E+01 Rb-86 2.56E-07 5.68E+05 Rh-103m O.OOE+OO O.OOE+OO Rh-105 8.74E-07 1.94E+06 Rh-106 1.0BE-06 2.40E+06 Ru-103 3.13E-06 6.95E+06 Ru-105 4.22E-06 9.37E+06 Sb-127 3.82E-06 8.48E+06 Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µ,Ci/cc) 80-82 Mirian 1-WRA713, 2-WRA-714 Detection Detection efficiency efficiency Nuclide

{cps/(Bq/m3)}

{cpm/( µCi/cc)}

Sb-129 5.56E-06 1.23E+07 Sr-89 2.89E-10 6.42E+02 Sr-91 4.SSE-06 1.01E+07 Sr-92 3.02E-06 6.70E+06 Tc-99m 2.37E-06 5.26E+06 Te-127 4.25E-08 9.44E+04 Te-127m 5.49E-10 1.22E+03 Te-129 3.87E-07 8.59E+05 Te-129m 1.32E-07 2.93E+05 Te-131m 6.53E-06 1.45E+07 Te-132 3.25E-06 7.22E+06 Xe-133 3.42E-09 7.59E+03 Xe-135 3.37E-06 7.48E+06 Y-90 3.83E-14 8.SOE-02 Y-91 7.49E-09 1.66E+04 Y-92 8.13E-07 1.80E+06 Y-93 4.56E-07 1.01E+06 Zr-95 3.11E-06 6.90E+06 Zr-97 3.82E-06 8.48E+06

Information PMP-6010-0SD-001 I Rev. 26 OFF-SITE DOSE CALCULATION MANUAL.13 Counting Efficiency for R-20, R-28, 1-WRA-713, 2-WRA-714, 1-WRA-717, and Mirion Nuclide Am-241 Ba-137m Ba-139 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Cs-134 Cs-136 Cs-137 1-131 1-132 1-133 1-134 l-135D Kr-85 Kr-85m Kr-87 R-28 replacement 1-WRA-717, 2-WRA-718 Detection Detection efficiency efficiency

{ cps/(Bq/m3)}

{cpm/( µCi/cc)}

7.29E-10 1.62E+03 1.71 E-05 3.80E+07 1.47E-06 3.26E+06 6.64E-06 1.47E+07 1.85E-06 4.11E+06 9.67E-06 2.15E+07 2.90E-07 6.44E+05 1.38E-10 3.06E+02 1.15E-10 2.55E+02 4.33E-05 9.61E+07 5.19E-05 1.15E+08 1.67E-05 3.71E+07 1.59E-05 3.53E+07 5.72E-05 1.27E+08 1.95E-05 4.33E+07 6.14E-05 1.36E+08 4.15E-05 9.21E+07

. 7.94E-08 1.76E+05 5.53E-06 1.23E+07 1.55E-05 3.44E+07 2-WRA-718 Mirion 1-WRA-717, 2-WRA-718 Detection Detection efficiency efficiency Nuclide

{cps/(Bq/m3)}

{cpm/( µCi/cc)}

Kr-88 2.45E-05 5.44E+07 La-140 4.13E-05 9.17E+07 La-141 4.33E-07 9.61E+05 La-142 2.90E-05 6.44E+07 Mo-99 7.11E-06 1.58E+07 Nb-95 1.98E-05 4.40E+07 Nd-147 3.34E-06 7.41E+06 Np-239 4.SOE-06 1.07E+07 Pr-143 2.40E-13 5.33E-01 Pr-144 4.93E-07 1.09E+06 Pu-238 6.0SE-11 1.35E+02 Pu-239 1.46E-09 3.24E+03 Pu-240 5.84E-11 1.30E+02 Pu-241 1.17E-11 2.60E+01 Rb-86 1.78E-06 3.95E+06 Rb-103m O.OOE+OO O.OOE+OO Rh -10 5 3.54E-06 7.86E+06 Rh -106 6.25E-06 1.39E+07

-Ru-103 1.74E-05 3.86E+07 Ru -10 5 2.23E-05 4.95E+07 Sb-127 2.07E-05 4.60E+07 Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc)

Mirion Nuclide Sb-129 Sr-89 Sr-91 Sr-92 Tc-99m Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 Xe-133 Xe-135 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 I

Page 82 of 98 Pages:

80-82 1-WRA-717, 2-WRA-718 Detection Detection efficiency efficiency

{ cps/(Bq/m3)}

{cpm/( µCi/cc)}

3.56E-05 7.90E+07 1.93E-09 4.28E+03 2.85E-05 6.33E+07 2.20E-05 4.88E+07 2.95E-06 6.55E+06 2.0SE-07 4.62E+05 3.25E-09 7.22E+03 2.0SE-06 4.55E+06 7.88E-07 1.75E+06 3.55E-05 7.88E+07 9.88E-06 2.19E+07 4.99E-09 1.11E+04 1.25E-05 2.78E+07 3.01E-13 6.68E-01 5.46E-08 1.21E+05 5.51E-06 1.22E+07 2.19E-06 4.86E+06 1.90E-05 4.22E+07 2.36E-05 5.24E+07

Information PMP-6010-0SD-001 I

Rev. 26 Page 83 of 98 OFF-SITE DOSE CALCULATION MANUAL.14 Gaseous Effluent Release Systems Page:

83 SOURCES WasteGasDecay SYSTEMS RELEASE POINTS TanksandCVCS r'.=,=====...

HUT Aux. Building Vent Feat uresVent System Fuel Handling Ventilation Containment Purge and Relief System Instrument Room PurgeSyst.em Steam General or Slowdown Treatment System Condenser Air Ejector System Gland Seal Condenser Exhaust

""--""'T--~

r*

'""-' -~--corl Fr~i:H~aders Ventilation

~

Pre HEPA FIiter Filter Pre HEPA

---

Jli> FIiter Filter HEPA Carbon Filter Filter

/ loampersl arbon tt-1--------------,PI Filter~

~

Airborne Lower Containment Radiation Monitors. Theselsolal&contalnment 1---------------2:!

S=:a'::m'::pl:::ln::g:=P:=ol':::n::::t ~L--.! Ins!:~~~:*,:~:~::::,,~;:~~:',: ::dhlgh Upper ContainmentArea R11dla1JonMonl1or. This Isolates eontainmont purge,ctmt.relief,and

~----~

aterm.

lnstrumon!room

~------------------------....::=========:::::'..--! oi.haustsonhlghalarm.

c QJ >

C

i 0 I-E C

QJ a::

Plant Vent to atmosphere

~1-----------------------------.i~I Ex~:::,o I atmosphere To Treatment System nogaseousretease I RowData r

I SampllnqPoint

~

St~::::::lr,~~_.1' ___________________________ ~~Q I SamplingPoiQI FlowData I I~ r------------,

I Local I r.is:..,~;;;a;;;:;;:.:;;;:;:;c:";n;;;g;-i*-----------,~__.'t F~I _Ra_d*_,~_tlo_n_~l~----------------.i~ a~:

0:~;;

0

Information PMP-6010-0SD-001 I

Rev. 26 Page 84 of 98 OFF-SITE DOSE CALCULATION MANUAL.15 Plant Gaseous Effluent Parameters

• Page:

84 SYSTEM UNIT EXHAUST CAPACITY FLOW RATE (CFM)

I PLANT AUXILIARY BUILDING 1

186,600 max UNIT VENT 2

143,400 max WASTE GAS DECAY TANKS (8) 1 125 4082 FT3 @100 psig AND CHEMICAL & VOLUME 28,741 ft3 max CONTROL SYSTEM HOLD UP

@ 8#, 0 level TANKS (3)

+ AUXILIARY BUILDING 1

72,660 EXHAUST 2

59,400

+ENG.SAFETY FEATURES 1&2 50,000 VENT

+ FUEL HANDLING AREA VENT 1

30,000 SYSTEM CONTAINMENT PURGE SYSTEM 1&2 32,000 CONTAINMENT PRESSURE 1&2 1,000 RELIEF SYSTEM INSTRUMENT ROOM PURGE 1&2 1,000 SYSTEM II CONDENSER AIR EJECTOR 2 Release Points SYSTEM One for Each Unit NORMAL STEAM JET AIR 1&2 230 EJECTORS START UP STEAM JET AIR 1&2 3,600 EJECTORS III TURBINE SEALS SYSTEM 1

1,260 2

5,508 2 Release Points for Unit 2 IV START UP FLASH TANK VENT 1

1,536 2

1,536

+ Designates total flow for all fans.

Information PMP-6010-0SD-001 I

Rev. 26 Page 85 of 98 OFF-SITE DOSE CALCULATION MANUAL.16 10 Year Average of 1995-2004 Data Pages:

85 - 86 x/Q GROUND AVERAGE (sec/m3)

DIRECTION DISTANCE (METERS)

(WIND FROM) 594 2416 4020 5630 7240 N

4.l?E-06 4.82E-07 2.25E-07 l.33E-07 9.32E-08 NNE 3.02E-06 3.64E-07 l.73E-07 l.04E-07 7.29E-08 NE 4.54E-06 5.31E-07 2.60E-07 l.59E-07 l.13E-07 ENE 7.16E-06 7.99E-07 4.04E-07 2.52E-07 l.80E-07 E

l.04E-05 l.13E-06 5.82E-07 3.66E-07 2.63E-07 ESE l.O?E-05 l.18E-06 6.04E-07 3.78E-07 2.72E-07 SE l.15E-05 l.24E-06 6.36E-07 4.00E-07 2.88E-07 SSE l.30E-05 l.42E-06 7.27E-07 4.57E-07 3.29E-07 s

l.41E-05 l.57E-06 7.92E-07 4.93E-07 3.54E-07 SSW 7.03E-06 7.81E-07 3.90E-07 2.41E-07 l.72E-07 SW 4.12E-06 4.73E-07 2.28E-07 l.38E-07 9.73E-08 WSW 3.29E-06 3.65E-07 l.76E-07 l.06E-07 7.52E-08 w

3.63E-06 4.llE-07 l.96E-07 1.18E-07 8.31E-08 WNW 3.02E-06 3.43E-07 l.61E-07 9.59E-08 6.71E-08 NW 3.22E-06 3.61E-07 l.71E-07 l.02E-07 7.16E-08 NNW 3.84E-06 4.29E-07 2.02E-07 l.20E-07 8.40E-08 DIRECTION DISTANCE (METERS)

(WIND FROM) 12067 24135 40225 56315 80500 N

4.64E-08 l.79E-08 8.89E-09 5.68E-09 3.56E-09 NNE 3.66E-08 1.43E-08 7.13E-09 4.56E-09 2.87E-09 NE 5.75E-08 2.30E-08 l.15E-08 7.41E-09 4.72E-09 ENE 9.30E-08 3.80E-08 l.91E-08 1.23E-08 7.90E-09 E

l.37E-07 5.65E-08 2.85E-08 l.83E-08 l.18E-08 ESE 1.41E-07 5.81E-08 2.93E-08 l.88E-08 l.22E-08 SE 1.50E-07 6.20E-08 3.12E-08 2.0lE-08 1.30E-08 SSE l.71E-07 7.06E-08 3.56E-08 2.29E-08 l.48E-08 s

l.84Es07 7.49E-08 3.77E-08 2.43E-08 l.56E-08 SSW 8.86E-08 3.59E-08 l.80E-08 l.15E-08 7.39E-09 SW 4.93E-08 l.96E-08 9.77E-09 6.27E-09 3.98E-09 WSW 3.80E-08 l.51E-08 7.53E-09 4.83E-09 3.0?E-09 w

4.l?E-08 l.64E-08 8.13E-09 5.20E-09 3.28E-09 WNW 3.34E-08 l.29E-08 6.41E-09 4.lOE-09 2.57E-09 NW 3.57E-08 l.39E-08 6.89E-09 4.41E-09 2.77E-09 NNW 4.19E-08 3.35E-08 8.lOE-09 5.19E-09 3.27E-09 DIRECTION TO - SECTOR N

= A E

= E s

= J w

= N NNE

= B ESE

= F SSW

= K WNW = p NE

= C SE

= G SW

= L NW

= Q ENE

= D SSE

= H WSW

= M NNW

= R Worst Case X /Q = 2.04E-05 sec/m3 in Sector H 2004

Information PMP-6010-0SD-001 I

Rev. 26 Page 86 of 98 OFF-SITE DOSE CALCULATION MANUAL.16 10 Year Average of 1995-2004 Data Pages:

85 - 86 D/Q DEPOSITION (1/m2)

DIRECTION DISTANCE (METERS)

(WIND FROM) 594 2416 4020 5630 7240 N

2.37E-08 2.29E-09 l.04E-09 5.44E-10 3.47E-10 NNE 9.86E-09 9.52E-10 4.32E-10 2.27E-10 l.45E-10 NE l.29E-08 l.25E-09 5.67E-10 2.97E-10 l.90E-10 ENE 1.59E-08 1.54E-09 6.97E-10 3.66E-10 2.33E-10 E

l.87E-08 l.81E-09 8.20E-10 4.30E-10 2.75E-10 ESE l.85E-08 l.79E-09 8.12E-10 4.26E-10 2.72E-10 SE l.90E-08 l.83E-09 8.30E-10 4.36E-10 2.78E-10 SSE 2.40E-08 2.32E-09 1.05E-09 5.52E-10 3.52E-10 s

3.68E-08 3.56E-09 l.61E-09 8.46E-10 5.40E-10 SSW 2.30E-08 2.22E-09 l.OlE-09 5.28E-10 3.37E-10 SW 2.22E-08 2.15E-09 9.74E-10 5.llE-10 3.26E-10 WSW

2. llE-08 2.04E-09 9.23E-10 4.84E-10 3.09E-10 w

2.00E-08 l.93E-09 8.74E-10 4.59E-10 2.93E-10 WNW 1.75E-08 1.69E-09 7.64E-10 4.0lE-10 2.56E-10 NW l.58E-08 1.53E-09 6.94E-10 3.64E-10 2.32E-10 NNW 2.30E-08 2.22E-09 l.OlE-09 5.28E-10 3.37E-10 DIRECTION DISTANCE (METERS)

(WIND FROM) 12067 24135 40225 56315 80500 N

1.45E-10 4.72E-11 1.74E-11 9.27E-12 4.65E-12 NNE 6.36E-11 l.97E-ll 7.24E-12 3.86E-12 l.94E-12 NE 8.07E-11 2.58E-ll 9.51E-12 5.07E-12 2.54E-12 ENE 9.77E-11 3.17E-ll 1.17E-ll 6.23E-12 3.13E-12 E

l.14E-10 3.73E-11 l.37E-ll 7.34E-12 3.68E-12 ESE l.13E-10 3.70E-11 l.36E-ll 7.26E-12 3.64E-12 SE l.16E-10 3.78E-ll l.39E-ll 7.42E-12 3.72E-12 SSE l.47E-10 4.79E-11 1.76E-11 9.41E-12 4.72E-12 s

2.25E-10 7.34E-11 2.70E-ll l.44E-11 7.23E-12 SSW l.41E-10 4.59E-11 l.69E-ll 9.0lE-12 4.52E-12 SW l.36E-10 4.43E-11 l.63E-11 8.71E-12 4.37E-12 WSW l.29E-10 4.20E-11 l.55E-11 8.26E-12 4.14E-12 w

l.22E-10 3.98E-11 l.47E-11 7.82E-12 3.92E-12 WNW 1.07E-10 3.48E-11 l.28E-11 6.84E-12 3.43E-12 NW 9.70E-11 3.16E-11 1.16E-11 6.20E-12 3.llE-12 NNW l.41E-10 4.58E-11 l.69E-11 9.00E-12 4.52E-12 DIRECTION TO - SECTOR N

= A E

= E s

= J w

= N NNE

= B ESE

= F SSW

= K WNW = p NE

= C SE

= G SW

= L NW

= Q ENE

= D SSE

= H WSW

= M NNW

= R Worst Case D/Q = 4.46E-08 l/m2 in Sector A 2001

Information PMP-6010-0SD-001 I

Rev. 26 Page 87 of 98 OFF-SITE DOSE CALCULATION MANUAL.17 Annual Evaluation of x/Q and D/Q Values For Page:

All Sectors 87

1.

Performed or received annual update of x/Q and D/Q values. Provide a description of what has been received.

I Signature Date Environmental Department (print name, title)

2.

Worst x /Q and D/Q value and sector determined. PMP-6010-0SD-001 has been updated, if necessary. Provide an evaluation.

I Signature Date Environmental Department (print name, title)

3.

Review nuclide mix for gaseous and liquid release paths to determine if the dose conversion factor of total body is still applicable. Provide an evaluation.

4.

Approved and verified by:

I Signature Date Environmental Department (print name, title)

I Signature Date*

Environmental Department (print name, title)

Information PMP-6010-0SD-001 I

Rev. 26 Page 88 of 98 OFF-SITE DOSE CALCULATION MANUAL.18 Dose Factors Pages:

88 - 89 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

TOTAL BODY SKIN DOSE GAMMA AIR BETA Am DOSE FACTOR FACTOR DOSE FACTOR DOSE FACTOR Ki (DFBi)

Li (DFSi)

Mi (DFYi)

Ni (DFPi) mrem m3 (mrem m3 (mrad m3 (mrad m3 RADIONUCLIDE per µCi yr) per µCi yr) per µCi yr) per µCi yr)

Kr-83m 7.56E-02 l.93E+Ol 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+Ol 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 l.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 l.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+Ol 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

• The listed dose factors are for radionuc!ides that may be detected in gaseous effluents, from Reg. Guide 1.109, Table B-1.

Information PMP-6010-0SD-001 I

Rev. 26 Page 89 of 98 OFF-SITE DOSE CALCULATION MANUAL.18 Dose Factors Pages:

88 - 89 DOSE FACTORS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, IN GASEOUS EFFLUENTS FOR CHILD*

Ref. 5.2.lee and ff Pi Pi INHALATION FOOD & GROUND PATHWAY PATHWAY RADIONUCLIDE (mrem m 3 (mrem m2 sec per µCi yr) per µCi yr)

H-3 1.12E+03 l.57E+03 u P-32 2.60E+06 7.76E+10 Cr-51 1.70E+04 1.20E+07 Mn-54 1.58E+06 1.12E+09 Fe-59 1.27E+06 5.92E+08 Co-58 1.11E+06 5.97E+08 Co-60 7.07E+06 4.63E+09 Zn-65 9.95E+05 1.17E+10 Rb-86 1.98E+05 8.78E+09 Sr-89 2.16E+06 6.62E+09 Sr-90 1.01E+08 1.12E+ 11 Y-91 2.63E+06 6.72E+06 Zr-95 2.23E+06 3.44E+08 Nb-95 6.14E+05 4.24E+08 Ru-103 6.62E+05 1.55E+08 Ru-106 1.43E+07 3.01E+08 Ag-llOm 5.48E+06 1.99E+10 I-131 1.62E+07 4.34E+ll I-132 1.94E+05 1.78E+06 I-133 3.85E+06 3.95E+09 I-135 7.92E+05 1.22E+07 Cs-134 1.01E+06 4.00E+lO Cs-136 1.71E+05 3.00E+09 Cs-137 9.07E+05 3.34E+10 Ba-140 1.74E+06 1.46E+08 Ce-141 5.44E+05 3.31E+07 Ce-144 1.20E+07 l.91E+08

• As Sr-90, Ru-106 and 1-131 analyses are performed, THEN use P, given in P-32 for nonlisted radionuclides.

1. The units for both H3 factors are the same, mrem m3 per µCi yr

Information PMP-6010-0SD-001 I

Rev. 26 Page 90 of 98 OFF-SITE DOSE CALCULATION MANUAL.19 Radiological Environmental Monitoring Program Pages:

Sample Stations, Sample Types, Sample Frequencies 90 - 93

[Ref 5 2 lw 5 2 ly 5 2 lu]

SAMPLE DESCRIPTION/

SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY ON-SITE AIRBORNE AND DIRECT RADIATION (TLD) STATIONS ONS-1 (T-1) 1945 ft@ 18° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radio iodine TLD Quarterly Direct Radiation Quarterly ONS-2 (T-2) 2338 ft @ 48° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radio iodine TLD Quarterly Direct Radiation Quarterly ONS-3 (T-3) 2407 ft @ 90° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-4 (T-4) 1852 ft.@ 118° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radio iodine TLD Quarterly Direct Radiation Quarterly ONS-5 (T-5) 1895 ft@ 189° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-6 (T-6) 1917 ft@ 210° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne I-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly T-7 2103 ft @ 36° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-8 2208 ft@ 82° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-9 1368 ft@ 149° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-10 1390 ft@ 127° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-11 1969 ft@ 11° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-12 2292 ft@ 63° from Plant Axis TLD Quarterly Direct Radiation Quarterly CONTROL AIRBORNE AND DIRECT RADIATION (TLD) STATIONS NBF 15.6 miles SSW Airborne Particulate Weekly Gross Beta Weekly New Buffalo, MI Gamma Isotopic Quart. Comp.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly SBN 26.2 miles SE Airborne Particulate Weekly Gross Beta Weekly South Bend, IN Gamma Isotooic Quart. Comp.

Airborne Radioiodine I-131 Weekly TLD Quarterly Direct Radiation Quarterly DOW 24.3 miles ENE Airborne Particulate Weekly Gross Beta Weekly Dowagiac, MI Gamma Isotopic Quart. Comp.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly COL 18.9 miles NNE Airborne Particulate Weekly Gross Beta Weekly Coloma, MI Gamma Isotopic Quart. Comp.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly

Information PMP-6010-0SD-001 I

Rev. 26 Page 91 of 98 OFF-SITE DOSE CALCULATION MANUAL.19 Radiological Environmental Monitoring Program Pages:

Sample Stations, Sample Types, Sample Frequencies 90 - 93 SAMPLE DESCRIPTION/

SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY OFF-SITE DIRECT RADIATION (TLD) STATIONS OFT-1 4.5 miles NE, Pole #B294-44 TLD Quarterly Direct Radiation Quarterly OFT-2 3.6 miles, NE, Stevensville TLD Quarterly Direct Radiation Quarterly Substation OFT-3 5.1 miles NE, Pole #B296-13 TLD Quarterly Direct Radiation Quarterly OFT-4 4.1 miles, E, Pole #B350-72 TLD Quarterly Direct Radiation Quarterly OFT-5 4.2 miles ESE, Pole #B387-32 TLD Quarterly Direct Radiation Quarterly OFT-6 4.9 miles SE, Pole #B426-1 TLD Quarterly Direct Radiation Quarterly OFT-7 2.5 miles S, Bridgman Substation TLD Quarterly Direct Radiation Quarterly OFT-8 4.0 miles S, Pole #B424-20 TLD Quarterly Direct Radiation Quarterly OFT-9 4.4 miles ESE, Pole #B369-214 TLD Quarterly Direct Radiation Quarterly OFT-10 3.8 miles S, Pole #B422-99 TLD Quarterly Direct Radiation Quarterly OFT-11 3.8 miles S, Pole #B423-12 TLD Quarterly Direct Radiation Quarterly GROUNDWATER (WELL WATER) SAMPLE STATIONS W-1 1969 ft @ 11 ° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-2 2302 ft@ 63° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-3 3279 ft @ 107° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-4 418 ft@ 301 ° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-5 404 ft @ 290° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-6 424 ft@ 273° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-7 1895 ft@ 189° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-8 1274 ft@ 54° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-9 1447 ft@ 22° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-10 4216 ft @ 129° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-11 3206 ft @ 153° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-12 2631 ft@ 162° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-13 2152 ft@ 182° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-14 1780 ft@ 164° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-15 725 ft @ 202° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-12C Tritium Quarterly W-16 2200 ft @ 208° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-20 Tritium Quarterly W-17 2200 ft@ 180° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-21 Tritium Quarterly

Information PMP-6010-0SD-001 I

Rev. 26 Page 92 of 98 OFF-SITE DOSE CALCULATION MANUAL.19 Radiological Environmental Monitoring Program Pages:

Sample Stations, Sample Types, Sample Frequencies 90 - 93 DRINKING WATER STJ St. Joseph Public Intake Sta.

Drinking water Once per calendar Gross Beta 14 day Como.

9mi.NE Day Gamma Isotopic 14 day Comp.

I-131 14 day Como.

Tritium Quart. Comp.

LTW Lake Twp. Public Intake Sta.

Drinking water Once per calendar Gross Beta 14 day Como.

0.6mi. S Day Gamma Isotopic 14 day Como.

I-131 14 day Comp.

Tritium Quart. Como SAMPLE DESCRIPTION/

SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY SURFACE WATER SWL-2 Plant Site Boundary - South Surface Water Once per calendar Gamma Isotopic Month. Comp.

500 ft. south of Plant Day Tritium Quart. Comp Centerline SWL-3 Plant Site Boundary - North Surface Water Once per calendar Gamma Isotopic Month. Comp.

500 ft. north of Plant Day Centerline Tritium Quart. Comp.

SEDIMENT SL-2 Plant Site Boundary - South Sediment Semi-Ann.

Gamma Isotopic Semi-Annual 500 ft. south of Plant Centerline SL-3 Plant Site Boundary - North Sediment Semi-Ann.

Gamma Isotopic Semi-Annual 500 ft. north of Plant Centerline INGESTION - MILK Indicator Farms.

Milk Once every 1-131 per sample 15 days Gamma Isotopic per sample Milk Once every I-131 per sample 15 days Gamma Isotopic per samole Milk Once every I-131 per samole 15 days Gamma Isotopic per samole INGESTION - MILK Background Farm' I

I Milk I

Once every 15 days I I-131 I per sample I Gamma Isotopic I per samole SAMPLE DESCRIPTION/

SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY INGESTION - FISH **

ONS-N 0.3 mile N, Lake Michigan Fish - edible portion 2/year Gamma Isotopic per samole ONS-S 0.4 mile S, Lake Michigan Fish - edible oortion 2/year Gamma Isotopic per sample OFS-N 3.5 mile N, Lake Michigan Fish - edible portion 2/vear Gamma Isotopic per samole OFS-S 5.0 mile S, Lake Michill:an Fish - edible portion 2/vear Gamma Isotopic per samole

Information PMP-6010-0SD-001 I

Rev. 26 Page 93 of 98 OFF-SITE DOSE CALCULATION MANUAL.19 Radiological Environmental Monitoring Program Pages:

Sample Stations, Sample Types, Sample Frequencies 90 - 93 INGESTION - FOOD PRODUCTS On Site ONS-G Nearest sample to Plant in the Food Products At time of Gamma Isotopic At time of highest D/Q land sector harvest harvest containing media.

ONS-V Broadleaf At time of Gamma Isotopic At time of vegetation harvest harvest Off Site OFS-G In a land sector containing Food Products At time of Gamma Isotopic At time of food products, approximately 20 harvest Harvest miles from the plant, in one of the less prevalent D/Q land sectors OFS-V Broadleaf At time of Gamma Isotopic At time of vegetation harvest harvest INGESTION - BROADLEAF IN LIEU OF GARDEN CENSUS OR IN LIEU OF MILK (*)

3 samples *of different kinds of broad leaf vegetation Broadleaf Monthly Gamma Isotopic Monthly collected at the site boundary, within five vegetation when available Il31 when available miles of the plant, in each of 2 different sectors with the highest annual average D/Q containing media 1 background sample of similar vegetation Broadleaf Monthly Gamma Isotopic Monthly grown 10-20 miles distant in one of vegetation when available 1131 when available the less prevalent wind directions.

Collect composite samples of Drinking and Surface water at least daily. Analyze particulate sample filters for gross beta activity 24 or more hours following filter removal. This will allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, perform gamma isotopic analysis on the individual samples.

• IF at least three indicator milk samples and one background milk sample cannot be obtained, THEN three broad leaf samples of different kinds will be collected in each of 2 different offsite locations, within five miles of the plant, with the highest D/Q (refers to the highest annual average ground D/Q). Also, one background broad leaf sample of similar kinds will be collected 10 to 20 miles from the plant in one of the less prevalent D/Q land sectors.

The three milk indicator and one background farm will be determined by the Annual Land Use Census and those that are willing to participate.

IF it is determined that the milk animals are fed stored feed, THEN monthly sampling is appropriate for that time period.

Evaluate samples that identified positive plant effluent related radionuclides and determine if additional analysis are necessary to identify hard to detect radionuclides. The 10 CFR 61 scaling factor report should be consulted along with the radioactive material shipping program owner and the ODCM program owner to assist with this determination.

• • Due to the transient nature of fish throughout the year due to lake temperatures and food supplies, it is acceptable to obtain fish sample from alternate locations so long as the intent of sampling fish from close to the plant site and samples of fish serving as a background exist.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 94 of 98 OFF-SITE DOSE CALCULATION MANUAL.20 Maximum Values for Lower Limits of Detections A,B - REMP Pages:

94-95

[Ref. 5.2.lw]

Radionuclides Food Product Water Milk Air Filter Fish Sediment pCi/kg, wet pCi/1 pCi/1 pCi/m3 pCi/kg, wet pCi/kg, dry Gross Beta 4

0.01 H-3 2000 Ba-140 60 60 La-140 15 15 Cs-134 60 15 15 0.06 130 150 Cs-137 60 18 18 0.06 150 180 Zr-95 30 Nb-95 15 Mn-54 15 130 Fe-59 30 260 Zn-65 30 260 Co-58 15 130 Co-60 15 130 1-131 60 1

1 0.07 This Data is directly from our plant-specific Technical Specification.

Information PMP-6010-0SD-001 I

Rev. 26 I Page 95 of 98 OFF-SITE DOSE CALCULATION MANUAL.20 Maximum Values for Lower Limits of Detections A,B - REMP Pages:

94-95 NOTES A. The Lower Limit of Detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will be detected with 95 % probability and 5 % probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation), the LLD is given by the equation:

LLD=

4.66a

• S E* V* 2.22

• Y* eH**i.\\t)

Where LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume). Perform analysis in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable. It should be further clarified that the LLD represents the capability of a measurement system and not as an after the fact limit for a particular measurement.

S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency of the detection equipment as counts per transformation (that is, disintegration)

V is the sample size in appropriate mass or volume units 2.22 is the conversion factor from picocuries (pCi) to transformations (disintegrations) per minute Y is the fractional radiochemical yield as appropriate

]... is the radioactive decay constant for the particular radionuclide

.1t is the elapsed time between the midpoint of sample collection (or end of sample collection period) and time of counting.

B.

Identify and report other peaks which are measurable and identifiable, together with the radionuclides listed in.20, Maximum Values for Lower Limits of Detections A,B - REMP.

a A 2.71 value may be added to the equation to provide correction for deviations in the Poisson distribution at low count rates, that is, 2.71 + 4.66 x S.

Information PMP-6010-0SD-001 I

Rev. 26 Page 96 of 98 OFF-SITE DOSE CALCULATION MANUAL.21 Reporting Levels for Radioactivity Concentrations Page:

in Environmental Samples 96 Radionuclides Food Product Water Milk Air Filter Fish pCi/kg, wet pCi/1 pCi/1 pCi/m3 pCi/kg, wet H-3 20000 Ba-140 200 300 La-140 200 300 Cs-134 1000 30 60 10 1000 Cs-137 2000 50 70 20 2000 Zr-95 400 Nb-95 400 Mn-54 1000 30000 Fe-59 400 10000 Zn-65 300 20000 Co-58 1000 30000 Co-60 300 10000 I-131 100 2

3 0.90 IF any of the above concentration levels are exceeded THEN see guidance contained in step 3.5.2a. for additional information.

Information.22 Well W-16 Well W-10 TLDHi AirONS-6 PMP-6010-0SD-001 I

Rev. 26 OFF-SITE DOSE CALCULATION MANUAL On-Site Monitoring Location - REMP CNS-South CNS-North Surface Water SWL-3 LEGEND ONS ONS-6: Air Sampling Station T-1 -T-12:

TLD Sampling Station W-1 -W-17:

REMP Groundwater Wells SWL-2, 3:

Surface Water Sampling Stations SL-2 SL-3:

Sediment Sampling Stations ONS-N & S: Fish sampling locations Page 97 of 98 Page:

97

Information PMP-6010-0SD-001 I

Rev. 26 Page 98 of 98 OFF-SITE DOSE CALCULATION MANUAL.23 Off-Site Monitoring Locations - REMP Page:

98 Legend Offsite REMP Monitoring Locations OFT-1 -OFT-11 : TLD Locations Background Air/TLD Stations Drinking Water Locations Indicator Milk Farm Locations Background Milk Farm Locations OFS Offsite Fish locations St Joseph Water Treatment Plant (STJ)

New Buffalo Substation

Background

Air/TLD CFS-North TLD OFT-3 TLD OFT-1 TLD OFT-2 TLD OFT-4 TLD OFT-9 TLD OFT-5 Lake Township Water Treatmen-Nuclear Plant Plant (L TW)

TLDOFT-7 TLD-OFT-10 TLD OFT-1 1 TLD OFT-8 TLD OFT-6 CFS-South,

Union Pier Laporte Background Milk Farm I Hwy2 Hwy35 ~

us 12 Coloma Substation Coloma Rd

) o,,.,

r Sodus Eau Hwy23

\\ /

20 Mile Radius L

\\ ~1*

' ri

\\

\\ \\

\\

\\

Kankakee Station

Background

Air/TLD M-51 Dowagiac Substation

Background

Air/TLD (DOW)

Colby St

REVISION

SUMMARY

Procedure No.:

PMP-6010-0SD-001 Rev. No.:

26

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification 10 CFR 50.59 is not applicable to this procedure revision. Per definition in Attachment 1 of PMP-2010-PRC-002. This is an administrative procedure governing the conduct of facility operations. Changes to this document are made in accordance with Technical Specification 5.5.1 and implemented through 12-EA-6090-ENV-114, Effectiveness Review for ODCM/PCP Programs.

Security review per PMP-2060-SEC-007 is not applicable to this procedure revision. All review responses of the pre-screening in Data Sheet 1 of PMP-2060-SEC-007 were "No" and peer reviewed per Step 3. 3.1.

Section 1. 0 -

Added note informing users This is an editorial change to ensure users that the revision reflects pending RMS understand that during the RMS replacement Project changes to upgrade the system to project there will be a transition period Mirion detectors.

where both old and new equipment guidance will be needed, so personnel will need to verify what plant equipment is installed and select the appropriate guidance.

Revised Table of Contents and renumbered Multiple Sections and Attachments required as needed; no margin marks used.

updating of titles and/or updating the contents contained inside which lengthened the documentation. This altered page numbering throughout.

3.1.2.c-Clarified step to describe typical Editorial correction to enhance activities involving draining Steam understanding, with no changes to intent.

Generators 3.2.1.d-Revised the step to reflect the Editorial correction to provide clarity once alteration from a single detector ( current) to the new detectors are installed. No changes a pair of redundant detectors (Mirion).

to intent made, as the requirements are true/

unchanged regardless of the number of detectors.

3.2.1 Basis Liquid-Updated to reflect Editorial change to allow the step to be pending changes and corrected reference.

correct regardless of RMS system equipment installed. No changes to intent. Corrected typo on the reference.

3. 3.1-Revised the step to reflect the pending Editorial correction to provide clarity once alteration for the various detectors (current) the new detectors are installed. No changes to replacement detectors (Mirion). Updated to intent made, and Titles revisions made to Attachment Titles as needed. Margin marks reflect the changing attachments.

used on affected sub-steps.

Office Information for Form Tracking Only - Not Part of Fonn This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval.

Page 1 of 4.

REVISION

SUMMARY

Procedure No.:

PMP-6010-0SD-001 Rev. No.:

26

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification 3.3.2-Revised the step to reflect the pending Editorial correction to provide clarity once alteration for the various detectors (current) the new detectors are installed. Title changes to replacement detectors (Mirion). Updated made to reflect the changing attachments.

Attachment Titles as needed. Margin marks used on affected sub-steps.

3. 5.1. b-Editorial correction to clarify the Reworded the step so that all bullets were step.

accounted for in the discussion, as the original wording left off discussion on the final bullet.

3. 9-Editorial revision of the step to enhance Sub-steps were reworded to provide clarity of requirements. Affected sub-steps clarification of intent, as the wording was are not margin marked.

confusing. The new sub-steps are phrased to reflect the actual processes we perform now and neither create nor remove any actual requirements.

5. 2.1. kk-Added reference step Added new Mirion detector reference for counter efficiencies..2-Rewritten to include Mirion Added new Mirion detector instruments and information. No margin marks used.

the appropriate guidance to be used once installed..3-Rewritten to include Mirion Added new Mirion detector instruments and information. No margin marks used.

the appropriate guidance to be used once

• installed..4-Rewritten to include Mirion Added new Mirion detector instruments and information. No margin marks used.

the appropriate guidance to be used once instal.led. Specific guidance provided allowing credit for local display units and computer based data displays (PPC/RadServe)..5-Rewritten to include Mirion Added new Mirion detector instruments and information. No margin marks used.

the appropriate guidance to be used once installed. Specific guidance provided allowing credit for local display units and computer based data displays (PPC/RadServe), and providing new surveillance requirements associated with the local displays and computer based data displays.

Office Information for Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval.

Page 2 of 4

REVISION

SUMMARY

Procedure No.:

PMP-6010-0SD-001 Rev. No.:

26

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration. 8-Rewritten to include Mirian information. No margin marks used..11-Added new tables and notes pertaining to the Mirian monitors. No margin marks used..12-Added new tables and notes pertaining to the Mirion monitors. No margin marks used..13-Added new tables and notes pertaining to the Mirion monitors. No margin marks used..19-Added notation"**" for Fish samples. No margin marks used.. 19-Editorial enhancement that replaced the term "grapes" with "food products". No margin marks used.

Justification Added new Mirion detector instruments, with no changes made to MRP or flowrates as these remain unaffected by the RMS project. Notes were updated to reflect new equipment and design.

Added the new detector efficiency data obtained from Mirion and performed unit conversions to align with US standards/

present Cook standards. Only RRS-lOOlA/B provided in this attachment as the other monitors are covered in following attachments.

Curves are not included for the Mirion detectors as actual data was available (previous curves created empirically).

Blowdown detectors formally in Att.#3.11 added here so all blowdown is located in one spot (blowdown detectors listed currently in Att.#3.11 will be replaced by ones listed here). Performed unit conversions to align with US standards/ present Cook standards.

Curves are not included for the Mirion detectors as actual data was available (previous curves created empirically).

Performed unit conversions to align with US standards/ present Cook standards.

Added note to provide additional flexibility when obtaining fish samples due to the transient nature of fish and issues with finding them in our fixed sample spots during sampling evolutions. This does not alter intent and will enhance compliance.

Replacement of the "grapes" with "food product" adds additional flexibility on food harvests which vary from season to season.

This does not alter intent and will enhance compliance with the Reg.Guide 1.109.

AR#2017-10263-6 Office Information for Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval.

Page 3 of 4

REVISION

SUMMARY

Procedure No.:

PMP-6010-0SD-001 Rev. No.:

26

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification.23-Editorial correction to fix Editorial correction to fix image labels.

several labels not showing correctly. No AR#2016-0951-1 margin marks used.

Office Information for Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval.

Page 4 of 4

REVISION

SUMMARY

Procedure No.:

PMP-6010-0SD-001 Rev. No.:

Title:

OFF-SITE DOSE CALCULATION MANUAL IMPLEMENTATION PLAN Summary of Change See Revision Summary for details.

Reason for Change See Revision Summary for details.

Implementation Schedule Procedure to be made effective following PORC and upon Plant Manager's approval.

Training Needs NIA Expiration Date NIA Required Basis Documents Update None Related Processes and Procedures 12-THP-6010-RPI-805, Radiation Monitoring System Setpoints 12-THP-6010-RPP-709, Radiation Monitoring System Liquid Effluent Alarm.

26 These procedures are being updated to reflect the new Mirion monitors and their efficiencies as noted in this procedure. Changes are being tracked by GTs entered in the Corrective Action Program.

Transition Plan Attachments from previous revision of 12-THP-6010-0SD-001 may be used subject to the conditions described in PMP-2010-PRC-003.

Related Equipment Modifications Installation of new Mirion radiation monitors in both units per EC-53363 and EC-53364.

Communication Plan Effective date of this revision will be communicated via email to interested groups.

Special Tools, Aids, Permits, Etc.

NIA Related Condition Reports GT 2018-9280; GT-2019-4064; GT 2015-4386; GT 2018-1751; GT 2016-0951-1, GT 2017-10263-6 Office Information for Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval.

Page 5 of 4