Text

Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm
	ML17332A249
Person / Time
Site:	Cook
Issue date:	08/03/1994
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
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ML17332A248	List: ML17332A247; ML17332A249; ML17332A252; ML17334B518;
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	12-PMP-6010-OSD, NUDOCS 9408190148
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~ NlCH)GiAN POWER DONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE COVER SHEET.

Instruction No 12 PMP 6010 OSD.001 Revision No.

OFF-SITE DOSE CALCULATIONMANUAL SCOPE OF REVISION Marginal markings were not used. Blennlal review. Incorporated new 10CFR20 requirements.

Incorporated Change Sheet 1. Deleted redundant Attachment.

Made grammatical and editorial changes to more accurately reflect wording in current technical specifications for Generic Letter.89-01.

SIGNATURES REVISION NUMBER Revision 7 PREPARED BY QUALITYASSURANCE SUPERINTENDENT APPROVA PLANT NUCLEAR SAFETY COMMITTEE PLANT MANAGER APPROVAL APPROVAL DATE EFFECTIVE DATE '408190148 940803 PDR " ADOCK. '05000315'""]'," 'i A

PDR

12 PMP 6010.OSD-001 LIST OF EFFECTIVE PAGES PAGE NUMB REVISION NUMBER EFFECTIVE CHANGE SHEETS INDEX Page 1 of 3

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~ OSD.001 LIST OF EFFECTIVE PAGES PAGE NUMBER Page 22 of 39, Page 23 of 39 Page 24 of 39 Page 25 of 39 Page 26 of 39 Page 27 of 39 Page 28 of 39 Page 29 of 39 Page 30 of 39 Page 31 of 39 Page 32 of 39 Page 33 of 39 Page 34 of 39 Page 35 of 39 Page 36 of 39 Page 37 of 39 Page 38 of 39 Page 39 of 39 ATTACHMENT 3.

REVISION NUMBER EFFECTIVE CHANGE SHEETS Revision 7

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12 PMP 6010.OSD.001 LIST OF EFFECTIVE PAGES PAGE NUMBE REVISION NUMBER EFFECTIVE CHANGE SHEETS TT C E T 3.23 Page 1 of 2 Page 2 of 2 ATTACHMENT 3.24 Page 1 of 1 ATTACHMENT 3.2S Page 1 of 1 Revision 7

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PMP 6010 OSD-001 INDIANA MICHIGAN POWER COMPANY DONALD C-COOK NUCLEAR PLANT OFF-SITE DOSE CALCULATION MANUAL Section Number INDEX Page 1.0 OBJECTIVE 2 '

REFERENCES

~

1 3.0 LIST OF ATTACHMENTS

~

2 4

0 DETAILS

~

4 4.1 Calculation of Offsite Doses 4

4.1.1 Gaseous Effluent Releases 4

4.1.2 Liquid Effluent Releases 9

4.2 Limits of Operation and Surveillances of the Effluent Release Points

.12 4.2.1 Radioactive Liquid Effluent Monitoring Instrumentation (3/4 ~ 3 ~ 3 ~ 9)

~

~ 12 4.2.2 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation (3/4

~ 3 ~ 3 ~ 10)

~

Liquid Effluents 4.2.3.1 Concentration Excluding Releases via the Turbine Room Sump Discharge 4.2.3.2 Concentration of Releases the Turbine Room Sump Discharge

~ 13

~ 14

~ 14 via

.14 4.2.3.3 Dose (3/4.11.1.2)

.15 4.2.3.4 Liquid Radwaste Treatment System (3/4.3.1.1.3)

.16 Page 1 of 3

Revision 7

PMP 6010 OSD.001 4.2.4 Gaseous Effluents

.17 4.2.4.1 Dose Rate

.17 4.2.4.2 Dose Noble Gases (3/4.11.2.2)

~

.18 4.2.4.3 Dose Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form (3/4

~ 1 1 o 2 ~ 3)

~

~ 19 4.2.4.4 Gaseous Radwaste Treatment (3/4.11.2.4)

.20 4.2.5 Radioactive Effluents - Total Dose (3/4'1')

~

~ 20 4.3 Calculation of Alarm/Trip Setpoints

..21 4.3 '

Liquid Monitors

.22 4.3.1.1 Liquid Batch Monitor Setpoint Methodology

.22 4.3.1.2 Liquid Continuous Monitor Setpoint. Methodology

.24 4.3.2 Gaseous Monitors

.25 4.3.2.1 Plant Unit Vent

.25 4.3.2.2 Waste.Gas.

Decay, Tanks.

.28 4.3.2.3 Containment Purge and Exhaust System

.29 4.3.2.4 Steam Jet Air Ejector System

.29 4.3.2.5 Gland Seal Condenser Exhaust

.30 4.3.2.6 Emergency Gaseous Setpoint Methodology

.31 Page 2 of 3

Revision 7

PMP 6010 OSD.001 4.4 Radioactive Effluents Tocal Dose

.32 4.5 Radiological Environmental Monitoring Pr ogram

~

.32 4.5.1 Purpose of the Radiological Environmental Monitoring Program

.32 4.5.2 Conduct of the Radiological Environmental Monitoring Program

.32 4.5.3 Annual Land Use Census

.34 4.5.4 Interlahoratory Comparison Progress 0

~

.35 4.6 Steam Generator Storage Facility Groundwater Radiological Monitoring Program

~

~ 35 4.6.1 Purpose of the Steam Generator

'torage Facility Groundwater

- Radiological Monitoring Program

.35 4.6.2 Conduct of the Steam Generator Storage Facility Groundwater Radiological Monitoring Program 4.7 Meteorological Model 4.8 Reporting Requirements

.36

.36 4.8.1 Annual Radiological Environmental Operating Report..........,.

.36 4.8.2 Annual Radiological Effluent Release Report 4.9 Reporting/Management Review 5.0 EFFECTIVE DATE

.37

.38

.39 Page 3 of 3

Revision 7

12 PMP 6010 OSD. 001 INDIANA MICHIGAN POWER COMP2QPC DONALD C ~

COOK NUCLEAR PLANT OFF SXTE DOSE CALCULATION MANUAL 1'

OBJECTIVE The Off-Site Dose Calculation Manual (ODCM) is a supporting document to the Radiological Effluent Technical Specifications (RETS),

as defined in NUREG-0472.

The ODCM contains the methodology 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 also presents a map of the radiological environmental monitoring 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.

1.1 The Radiation Protection Department.

and the Radiological Support Section are responsible for implementation of the Off-Site Dose Calculation Manual.

The Radiological Support Section conducts periodic reviews and updates of the ODCM.

Any change will be reviewed and approved by the Radiological Support Section Manager.

2 '

REFERENCES 2.1 10CFR20, Standards for Protection Against Radiation.

2.2

10CFR50, Domestic Licensing of Production and Utilization Facilities.

2.3 PMI 6010, Radiation Protection Plan 2.4 NUREG-0472 2.5 NUREG-0133 2.6 Regulatory Guide 1.109.

2.7 Regulatory Guide 1.111.

2.8 Regulatory Guide 1.'13.

Page 1 of 39 Revision 7

12 PMP 6010 OSD.001 2.9 Final Safety Analysis Report (FSAR).

2. 10 2'1 Technical Specifications, Appendix A, Sections 6.8.1.e and 6.15, Offsite Dose Calculation Manual.

Final Environmental Statement D.

C.

Cook Nuclear Plant, August. 1973.

2.12 NUREG-0017 2.13 Correspondence:

D. "Noble to W. MacRae, "Referenced Efficiencies for RRS-1001", July 21, 1989.

2.14 ODCM Setpoints for Liquid Effluent Monitors (Bases), ENGR 107-04 8112.1 Environs Rad Monitor.

System.

2 15 Radiological Support Section Calculation RS-C-0202, July 31, 1989.

2.16 Radiological Support Section Calculation RS-C-0106, March 19, 1987.

2 ~ 17 "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 Offsite Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01)", United States Nuclear Regulatory Commission, January 31,1989.

2.18 12 THP 6010 RPP.601 Preparation of the Annual Radioactive Effluent Release Report.

3 '

LEST OF ATTACHMENTS

3. 1 Site Specific Parameters for the MIDAS Program 3.2 Radioactive Liquid Effluent Monitoring Instrumentation (Table 3.3-12) 3.3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements (Table 4.3-8) 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation (Table 3. 3-13) 3.5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements (Table 4.9-3)

Page 2 of 39 Revision 7

12 PMP 6010 OSD.001 3-..6-Radioactive Liquid Waste Sampling and Analysis Program (Table 4.11-1) 3.7 Radioactive Gaseous Waste Sampling and Analysis Program (Table 4.11-2) 3.8 Multiple Release Point Factors for Liquid Release Points 3.9 Liquid Effluent System Diagram 3.10 Plant Liquid Effluent Parameters 3.11 Counting Efficiency Table for RRS-1001

'3.12 Counting Efficiency-Curve for R-19, R-24 3.13 Counting Efficiency Curve for R-20, R-28

3. 14 Gaseous Effluent System Diagram 3.15 Plant, Gaseous Effluent Parameters

3. 16 Meteorological Parameters 3 ~ 17

3. 18 Annual Evaluation/Update of g/Q and D/Q Values for"all Sectors Dose Factors for Noble Gases and Daughters, Radioiodines and Radioactive Particulates, and Gaseous Effluents 3.19 Sampl'e Locations and Requirements for the REMP 3.20 Maximum Values for the Lower Limits of Detection 3.21 Reporting Levels for Radioactive Concentrations in Environmental Samples,

3.22 On Site Monitoring Locations 3.23 Off Site Monitoring Locations 3.24 3.25 Steam Generator Storage Building Monitoring Locations Steam Generator Storage Facility Radiological Monitoring Program Page 3 of 39 Revision 7

12 PMP 6010 OSD.001 4 '

DETAILS 4.1 Calculation of Offsite Doses 4.1.1 Gaseous Effluent Releases The calculation of doses from effluent releases is.

performed by the program MIDAS (Meteorological Information and Dose Assessment System).

The site specific parameters associated with MIDAS are shown in Attachment 3.1 for the following subprograms:

MIDER MZDEX MZDEL MIDEG MZDEN The subprogram used to enter and edit gaseous release data is called MD1EQ (EQ).

The data entered in EQ can be used to calculate the accumulation of dose to individual receptors based on hourly meteorology and release data.

The air dose from this data xs calculated via the XDAIR subprogram in MIDAS.

Zt. computes air dose results

..for use in Regulatory Guide 1.21 reports and Appendix I calculations based on routine releases.

The formula used for the calculation of the air dose is taken from Reg.

Guide 1.109:

D, B, air = X/Q Z{(M< or N<) x Q< x t x 3.17E

]

D, B, air

=

the gamma or beta air dose in mRad to an individual receptor.

x/Q M

N, Q<

3.17E

'he annual average or repl time atmospheric dispersion factor, sec/m the gamma air dose factor, mRad - m~, from. 18 sec -

@CD.18 sec - pCx the release of radionuclide, i, in pCi/sec duration of the release in seconds inverse number of seconds'/year, years/second.

Page 4 of 39 Revision 7

12 PMP 6010 OSD.001 The value for the X/Q is determined using equations 3 and 9 of Reg.

Guide 1.111 as shown below:

where:

H E

'~ minimum of a~+or Z 2'5 x

=

distance downwind of the source, meters.

This information is found in parameter 5 of MIDEX.

u

~ vind speed for ground release, meters/second.

Pg oy and o~ are di spersi on coeffien ts taken from R6 1 ~ 1 09 Vg H, =

building height from parameter 28 of MIDER.

terrain factor

(= 1 for Cook Nuclear Plant) because we consider all our releases to be ground level (see parameter g5 in MIDEX).

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 isotope for each pathway,

organ, age group, distance, and direction.

Calculations are based on the environmental pathways-to-man models in RG 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.

The equation used to calculate the dose in mRem is:

Total Bod Plume Pathwa mRem Dose (mRem) 3'17E g (Ql

+ g/g + SL

~ DFBf ~ t 3.17E where:

C1 sec Page 5 of 39 Revision 7

12 PMP 6010 OSD-001 S-f DFB; Q(

x/Q =

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 RG 1.109) the whole body dose factor from Table B-1 of Regulatory Guide 1.109.

the release rate of radionuclide i, in Curies/second the annual average or repl time atmospheric dispersion factor, sec/m t = duration of release, in seconds Skin P ume Pathwa mRem Dose (mRem)

~ 3,17E4 x 1.11 x Sz x t x ~ x tZ(g< x DFI)

+ Z(g< x DFS<)]

Where:

3. 17E 1 ~ 1 1 Q;

x/Q =

Sf DF" DFS C1 sec conversion factor, tissue to air,

~mRe mRad release rate of radionuclide i, in Curies/year.

the annual average OR real fime atmospheric dispersion factor, in sec/m.

shielding factor, that accounts for dose reduction due to shielding provided by residential structures during occupancy, 0.7 per Table E-15, RG 1.109.

duration of release',

seconds the gamma air dose factor for a uniform semi-infinite cloud of radionuclide i, in mRad

-m /pCi yr from Table B-l, RG 1.109.

the beta skin dose factor fop a semi-infinite cloud of radionuclide i, in mRem-m /pCi-yr from Table B-1, RG 1.109.

Radionuclide and Radioactive Particulate Doses The dose, in D>~ in mRem, to an individual from radionuclides, other than noble gases, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas will be determined as follows:

Dz~

3

~ 17E '(Ri x V x gal)

Page 6 of 39 Revision 7

12 PMP 6010 OSD. 001 where:

the most restrictive dose factor for each identified radionuclide i, in m~ mRem/yr per pCi/sec (for food and ground pathways) or mRem/yr per pCi/m (for inhalation pathway), for the appropr1ate pathway.

For sectors with existing pathways within 5 miles of the

site, use the values of R for these real pathways, otherwise use pathways distance of 5 miles.

See Attachment 3.1, page 22 of 27 for the maximum R-values for the most controlling age group for selected rad1onuclides.

R values were generated by computer code

PARTS, see NUkEG-0133, Appendix D.

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:

W<=

~x for the inhalation pathway, in sec/m3.

W<

=

Djg for the food and ground pathways in 1/m~

the release of those radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight (8) day, in pCi.

inverse number of seconds in a year, years/second.

In addition to the above routines, the QUICKG routine of the MIDAS system is used to provide data used in the monthly reports because of its s1mplicity compared to the process described above.

The QUICKG routine 1s based on NUREG 0133 methodology instead of the RG 1.109 methodology.

The equations used are as follows:

Gamma Radiat'on Dose GD -

round release 6D 3. 17E (Mg X/g Qg) taken from NUREG 0133, Section

5. 3. 1 (a)

~

Beta Radiation Dose BD round release BD ~ 3

~ 178 (H) s g/g

~ g))

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.

Page 7 of 39 Revision 7

12 PMP 6010 OSD ~ 001 where:

M, =

N, =

air dose factor due to gamma emissions for each noble gas radionuclide, i.

These factors are listed in.18, parameter 4 of MIDEN and are taken from Table B-1 of RG 1.109 air dose factor due to beta emissions for each noble gas radionuclide, i.

These factors are listed in.18, parameter 4 of MIDEN and are taken from Table B-1 of RG 1.109.

X/Q the average annual op real time relative concentration, sec/m for vent releases.

These factors are taken from parameter 9 of MIDEN or.16.

Q)

The amount of noble gas radionuclide released, pCi/sec.

Calculated via the MD1EQ/MD1AG pathway from plant release data sheets.

STEAM GENERATOR BLOWDOWN SYSTEM START UP FLASH TANK VENT The amount of radioiodine released via the start up calculated through actual flash tank is in service.

and other radionuclides that, are flash tank and it's.vent are sample results while the start up The following calculation is performed to determine the amount of curies released through this pathway.

Curies

= ~ x GPM x time on flash tank (min) x 3.785Z

'l The flow rate is determined from the blowdown.valve position chart recorder and the time on the start up tank is determined from the control room logs.

Chemistry department performs the sampling and analysis of the samples.

I This data is provided to the MIDAS computer and a dose calculation is performed to ensure compliance with Technical Specification 3/4.11.2.3 dose limits., MIDAS uses the formulas given in section 4.1.2 to calculate these doses to the public.

NOTE THIS SECTION PROVIDES THE MINIMUM REQUIREMENTS TO BE FOLLOWED AT COOK PLANT.

THIS WOULD BE USED IF ACTUAL SAMPLE DATA WAS NOT AVAILABLEEACH TIME THE START UP FLASH TANK WAS IN SERVICE.

Release rate of radioiodine via the Start Up Flash Tank must comply with Technical Specification 3/4.11.2.3.

Page 8 of 39 Revision 7

12 PMP 6010 OSD.001 The radioiodine release rate must be determined in accoxdance with the following equation every 31 day period whenever the specific activity of the secondary coolant system is greater than 0.01 uCi/gram dose equivalent I-131.

If the specific activity of the secondary coolant system is less than 0.01 uCi/gram dose equivalent Z-131, the release rate must be determined once every six months.

Q

=

(Ci)

(IPF)

(R

~)

Where:

Q

=

The release rate of I-131.from the steam generator flash tank vent, in uCi/sec.

Ci the concentration

.(uCi/cc) of I-131 in the secondary coolant averaged over a period not exceeding seven days'PF

=

the iodine partition factor fox the Start Up Flash Tank, 0.05, in accordance with NUREG-0017.

R, > =

the steam generator blowdown rate to the start up flash tank, in cc/sec.

The calculated release rate shall be assumed, to be the release rate until the next determination and used in the monthly dose projections to ensure compliance with Technical Specification 3/4.11.2.3.

The release rate calculations squall be reported in the annual effluent report.

I Steam Generators axe sparged, sampled and drained as batches early in outages to facilitate cooldown for entry into the steam generator.

This is repeated prior to startup to improve steam generator chemistry for the startup.

Liquid Effluent Releases 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 MD1EB (EB).

To calculate the individual doses (in 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 to be used can be selected using the MIDEL progiam by changing the values given in parameter 1.

Cook Nuclear Plant uses 3 pathways:

potable water, shoreline, and aquatic foods (fresh water sport fishing).

Page 9 of 39 Revision 7

12 PMP 6010 OS'01 The equations used are taken from RG 1.109 Appendix A.

They are as follows:

Potable Water where:

~pj op MP 2.23E' Q) afpj 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.

a usage factor that specifies the exposure time or intake rate for an individual of age group "a" associated with pathway "p".

Given in f29-84 of parameter 4 in MIDEL and R.G.

1.109 Table E-5.

the dilution factor at the point of exposure (or the oint of withdrawal of drinking water or point of arvest of aquatic food).

Given in parameter 5 of MIDEL as 2.6.

the dilution water flow rate in gpm conversion factor, ft3 m sec g

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

The values are taken from tables E-11 through E-14 of RG 1.109 and are located within the MIDAS code the radioactive decay constant for radionuclide i, in hours the average transit time required for nuclides to reach the point of exposure, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

For internal dose, t is the total elapsed time between release of the nuclides and ingestion of food or water, in hours.

Given as g25 of parameter 4 in MIDEL.

Page 10 of 39 Revision 7

12 PMP 6010 OSD. 00"

-=-.A a&.c Foods

,,p.,

M+ 2.23E

~ ~

where:

Bi t

P MP the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota fin pCi/kg) to the radionuclide concentration zn water (in pCi/liter) in liters/kg.

The factors are located within the MIDAS code and are taken from Table A-1 of RG 1.109 the average transit time required for nuclides to reach the point of exposure, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

For internal dose, t is the total elapsed between release of the nuclide% and ingestion of food or water, in hours.

Given as g26 of parameter 4 in MIDEL.

the dilution factor at the point of exposure, 1.0 for Aquatic Foods.

Shore ine De osits P

MjZ2.23E where:

the shoreline width factor.

Given as an input when running the program as 0.3 based on Table A-2 in RG 1.109 the radioactive half-life of the-nuclide, i, in days the period of time for which sediment or soil is exposed to the contaminated water, 1.31E'ours.

Given in MIDEL as item 6 of parameter 4.

the average transit time required for nuclides to reach the point of exposure, 0 hours0 days 0 hours 0 weeks 0 months .

Given as g28 of parameter 4 in MIDEL.

Page 11 of 39 Revision 7

12 PMP 6010 OSD- 001 The program MIDAS uses the following plant specific parameters which are inputted by the operator.

Irrigation rate = 0.0 Fraction of time on pasture

= 0.0 Fraction of feed on pasture

= 0.0 Shore width factor = 0.3 (from Reg.

Guide 1.109, Table A-2)

The results of DS1LI are printed in LDRPT (LP).

These results are used in the monthly repor on liquid releases.

Zn addition, the program DOSUM (DM) is used to search the results files of DS1LZ to find the maximum liquid pathway individual doses.

The highest exposures are then printed in a one page summary table.

Each lane is compared with the appropriate dose limit.

The table printed'provides a concise-summary of off site environmental dose calculations for inclusion in Regulatory Guide 1.21 reports.

4.2 Limits of Operation and Surveillances of the Effluent Release Points 4 2.1 Radioactive Liquid Effluent Monitoring Instrumentation (3/4 ' ' ')

4.2.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 3.2 shall be operable with their alarm/trip setpoints set to ensure that the limits of section 4.2.3.1 are not exceeded.

4.2.1.2 The applicability of each channel is shown in.2.

4.2.1.3 4.2.1.4 4.2.1.5 With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which wz.ll ensure that the limits of section 4.2.3.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, and reset or declare the monitor inoperable.

With one or more radioactive liquid effluent monitoring instrumentation. channels.inoperable, take the applicable action shown in Attachment 3.2.

The provision of the Technical Specifications 3.0.3 and 3.0.4 are not applicable.

4.2.1.6 The setpoints shall be determined in accordance with the methodology as described in section 4.3,.1.

The setpoints'sha3.1 be recorded.

Page 12 of 39 Revision 7

12 PMP 6010 OSD ~ 001 4.2.1.7 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check<

source

check, channel calibration and channel functional test at the frequencies shown in Attachment 3.3.

4.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation (3/4 ' ' '0) 4.2.2.1 The radioactive gaseous process and effluent monitoring instrumentation channels shown in.4 shall be operable with their alarm/trip setpoints set to ensure that the limits of section 4.2.4.1 are not exceeded.

4.2.2.2 The applicability of each channel is shown in.4.

4.2.2.3 With a radioactive gaseous process or effluent monitorinq instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of section 4.2.4.1 are met, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, and reset or declare the channel inoperable.

4.2.2.4 With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels

operable, take the action shown in Attachment 3.4.

4.2.2.5 The provisions of the Technical Specifications 3.0.3 and 3.0.4 are not applicable.

4.2.2.6 4 '.2.7 The setpoints shall be determined in accordance with the methodology as described in section 4.3.2.

The setpoint shall be recorded.

This surveillance requirement does not apply to the Waste Gas Holdup Syst: em Hydrogen and Oxygen Monitors; as their setpoints are not addressed in this document.

Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL

CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Attachment 3.S.

I Page 13 of 39 Revision 7

12 PMP 6010 OSD - 001 4.2.3.2.3 4.2.3.2.4 4 '.3.2.5 4.2.3.2.6 With releases from the Turbine Room Sump exceeding the above limits, perform a dose projection due to liquid releases to UNRESTRICTED AREAS to determine if the limits of Section 4.2.3.3.1 of the ODCM have been exceeded.

If the dose limits are exceeded, follow the direction of the action statements following Section 4.2.3.3.3.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Attachment 3.6.

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

(3/4 I,X 1 2) 4.2.3.3 Dose 4.2.3

~ 3 ~ 1 4.2.3.3.2 The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas (see Technical Specifications Figure 5.1-3) shall be limited during any calendar quarter to ~ 1.5 mRem to the total body,and to <

5 mRem to any organ, and during any calendar year to 3

mRem to the total Body and to

< 10 mRem to any organ.

These limits are applicable at all times.

Page 15 of 39 Revision 7

12 PMP 6010 OSD.001 4.2.3.3.3 4.2.3.3.4 4.2.3.3.5 With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions taken to assure that subsequent releases will be within the above limits.

This Special Report shall also include (1) the results of radiological analyses of the drinking water source, and (2) the radiological impacts on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

(Applicable only if drinking water supply is taken from the receiving water body.)

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

Cumulative dose contributions from liquid effluents shall be determined in accordance with this document at least once per 31 days.

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

4.2 '.4 Liquid Radwaste Treatment System (3/4.11.1.3) 4.2.3.4.1 4.2.3.4.2 The liquid radwaste treatment system shall be used to reduce, the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Technical Specifications Figure 5.1-3) when averaged over 31 days, would exceed 0.06 mRem to the total body or 0.2 mRem to any organ.

This section is applicable at all times.

Page 16 of 39 Revision 7

12 PMP 6010 OSD-001 4.2.3.4.3 With radioactive liquid waste being

,discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes the following information:

(1) Identification of the inoperable equipment or subsystems and the reason for inoperability, (2) Action(s) taken to restore the inoperable equipment to operable status, and (3)

Summary description of action(s) taken to prevent recurrence.

4.2.3.4.4 The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

4 '.3.4 '

Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with this document, whenever liquid releases are being made without being processed by the liqu1d radwaste treatment system.

4.2.4 Gaseous Effluents 4.2.4.1 Dose Rate (3.11.2.1) 4.2 '.1.1 The dose rate.due to radioactive materials released in gaseous effluents from the site (Technical Specification Figure 5.1-

3) shall be limited to

< 500 mRem/yr to the total body and

< 3000 mRem/yr to the skin for noble gases.

The dose rate due to all radioiodznes and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than 8 days shall be limited to <1500 mRem/yr to any organ.

4.2.4.1.2 This section is applicable at all times.

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

Page 17 of 39 Revision 7

12 PMP 6010 OSD.001 4.2.4.1.4 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in-accordance with the methods and procedures described in this document.

4.2.4.1.5 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined 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.

4.2.4.2 Dose - Noble Gases (3/4.11.2.2) 4.2.4.2. 1 V

4.2.4.2.2 4.2.4.2.3 4.2.4.2.4 4.2.4.2.5 The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be limited during any calendar

quarter, to <

5 mRad for gamma radiation and 5 10 mRad for beta radiation and during any calendar year, to

< 10 mRad for gamma radiation and g 20 mRad for beta radiation.

This section is applicable at all times.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special report which identifies the cause(s) for exceedingthe limit(s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be within the above limits.

The provisions of Technical Specification 3.0.3 and 3.0.4-are not.applicable.

Cumulative dose contributions for the total time period shall be determined in accordance with this document at least once every 31 days.

Page 18 of 39 Revision 7

12 PMP 6010 OS'01

- -4.2.4.3 Dose - Zodine-131, Zodine-133/ Tritium, and Radioactive Material in Particulate Form (3/4 11.2.3) 4.2.4.3. 1 The dose to a MEMBER OF THE PUBLlC from radioiodine, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (site boundary) shall be limited to the following:

(a) During any calendar quarter to less than or equal to 7.5 mRem to any organ, (b) During any calendar year to less than or equal to 15 mRem to any. organ, and (c) Less than 0. 14 of the limits of (a) and (b) above as a result of burning contaminated oil.

4.2.4.3.2 This section is applicable at all times.

4.2.4.3.3 4.2.4.3.4 4.2.4.3.5 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 to the Commission within 30

days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to assure that subsequent releases will be within the above limits.

The provisions of Technical Specification 3.0.3 and 3.0.4 are not applicable.

Cumulative dose contributions for the total time period shall be determined in accordance with this document at least once every 31 days.

Page 19 of 39 Revision 7

12 PMP 6010 OSD. 001 4.2.4.4 Gaseous Radwaste Treatment (3/4.11.2.4) 4.2.4.4.1 The gaseous radwaste treatment system and the ventilation exhaust treatment syst2em shall be used 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 (see Technical Specifications Figure 5.1-3) when averaged over 31 days, would exceed 0.2 mRad for gamma radiation and 0.4 mRad for beta

.- radiation.

The ventilation exhaust treatment, system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas (see Technical Specifications Figure 5.1-3) when averaged over 31 days would exceed 0.3 mRem to any organ.

4.2.4.4.2 This section is applicable at all times.

4.2.4.4.3 With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information:

(a) Identification of the inoperable equipment or subsystems and the reasons for inoperability.

fb) Act>on (s) taken to restore the inoperable equipment to operable status.

4.2.4.4.4 The provisions of Technical Specification 3.0.3 and 3.0.4 are not applicable.

4.2.4.4.5 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with this document, whenever the gaseous waste treatment system or ventilation exhaust treatment system is not operational.

4.2.5 Radioactive Effluents - Total Dose (3/F 11.4) 4.2.5.1 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 lim1ted to < 75 mRem) over a period of 12 consecutive months.

4.2.5.2 This section is applicable at all times.

Page 20 of 39 Revision 7

12 PMP 6010 OSD.001 3 With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of sections 4.2.3.3, 4.2.4.2 or 4.2.4.3, in lieu of any other report required by Technical Specification 6.9.2, prepare an8 submit a Special Report to the Director, Nuclear Reactor Regulation, U.

S. Nuclear Regulatory Commission, Washington D.

C.

20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above.

This Special Report shall include an analyses which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits above<

and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the special report shall include a request for a variance xn accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11fb).

Submittal of the report is considered a txmely

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 part 20, as addressed in other

'sections of this section.

4.2.5.

4.2.5.4 The provisions of Technical Specification 3.0.3 and 3.0.4 are not applicable.

4. 2. 5. 5 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with this document (including Sections 4.2.3.3, 4.2.4.2 and 4.2.4.3).

4.3 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 10CFR20 Appendix B Table II.

Setpoints shall be established 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 the setpoint calculations is the multiple release point factor (MRP).

The MRP is a factor used such that when all the releases are integrated, the applicable LIMIT value will not be violated.

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 Attachments 3.8.

Page 21 of 39 Revision 7

12 PMP 6010 OSD.001 4;.3.1 Liquid. Monitors Liquid monitor setpoints shall be established for each monitor of the liquid effluent release systems.

A schematic of the liquid effluent release systems is attached as.9.

A list of the Plant Liquid Effluent Parameters is in Attachment 3.10 The exact details of each system design and operation can be found in the system descriptions.

The setpoints are intended to help keep releases within the limits of 10CFR20 Appendix B, Table II, Column 2.

Setpoints shall be determined using one of two different methodologies, either the batch methodology or the continuous methodology.

4.3.1.1 Liquid Batch Monitor Setpoint Methodology There is only one monitor used on the liquid batch release system.

That monitor is used on the liquid waste discharge

system, and it is identified as RRS-1000.

The function of the monitor 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 flow rates and dilution flow rates are then adjusted to keep the release within the limits of 10CFR20.

Based on the concentrations of nuclides in the release the count rate on the monitor can be predicted.

The high alarm setpoint is then set at 1.5 times the predicted value up to the maximum setpoint of the system.

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.

The flow rates are determined in order to keep the release within the requirements of 10CFR20 Appendix B, Table II, Column 2.

The equation,to calculate the flow rates 1s:

LZMITg MRP Where:

C(

LIMIT, =

the concentration of nuclide i.

the 10CFR20 Appendix B, Table II, Column 2

limit of nuclide i.

the effluent flow rate in GPM (Attachment 3.10).

Page 22 of 39 Revision 7

12 PMP 6010 OSD.001 the dilution water flow rate as estimated prior to release.

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

the multiple release point factor.

A factor such that when all the release

~

oints are operating at one time'the imits of 10CFR20 wall not be exceeded.

This equation shall be true during the batch release.

Before the -release is started, the maximum effluent flow rate and the minimum dilution flow rate should be substituted for f and F, respectively.

Zf the equation is true, the release can proceed with those flow rates as the limits of operation.

Zf the equation is not true< the effluent flow rate can be reduced or 0he dilution flow rate can be increased to make the equation true.

This equation may be rearranged to solve for the max'mum effluent release flow rate (f).

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

The setpoint xs 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 nuclide to counts per unit of time as per Attachment 3.11.

The sum of all the counts per unit of time is the predicted

count, rate.

The predicted count rate is then multiplied by 1.5 to determine the high alarm setpoint.

Page 23 of 39 Revision 7

12 PMP 6010 OSD.001 4.3.1.2 Liquid Continuous Monitor Setpoint Methodology There are eight monitors used as continuous liquid release monitors.

These monitors are used in the steam generator

blowdown, blowdown treatment and essential service water systems.

The monitors are identified as:

o R-19 for the steam generator blowdown for both units.

~

o R-24 for the blowdown treatment system for both units.

o R-20 for the east ESW system for each unit.

o R-28 for the west ESW system for each unit.

The function of the monitors is to assure that releases are kept within the limits of 10CFR20 Appendix B, Tab1e II.

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

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

The setpoint for the continuous monitors is:

S LZMZTi E MRP P

f where:

S P LIMIT the setpoint of the monitor the calculated. limit of 1.5x10 5 based on a historical average of nuclides or the lowest limit from 10CFR20 Appendix B Table Il, Column 2 of a known possible nuclide in the effluent stream.

the effluent flow rate in GPM.

For routine operation, the setpoint should be calculated using the maximum effluent flow rate (Attachment 3.10).

Page 24 of 39 Revision 7

12 PMP 6010 OSD.001 F =

the dilution water flow rate as estimated prior to release.

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

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

MRP =

the multiple release point factor.

A factor such that when all the release

~

oints are operating at one time the imits of 10CFR20 wall not be exceeded.

(Attachment 3,8)

The list of known nuclides for the LIMIT factor in the above equation is given in Attachment 3.11.

The list.was generated from historical data of nuclides released from the plant, and is verified periodically and updated when needed.

The setpoint value is converted from pCi/ml to CPM using the attached efficiency curves for each monitor, Attachments 3.12 and 3.13, or by multiplying the concentration by the efficiency of the monitor.

4.3.2 Gaseous Monitors For the purpose of implementing sections 4.2.2 and 4.2.4.1, the alarm setpoints for gaseous effluents released into unrestricted areas will be established using the following methodology.

In addition, the above sections 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..15 presents the effluent flow rate parameter.

4.3.2.1 Plant Unit Vent The gaseous effluents discharged from the plant vent will be monitored by the plant vent radiation monitor low range noble gas channel

[Tag No. VRS-1505 (Unit 1), VRS-2505 (Unxt 2)] to assure that, alarms and trip actions (isolation of gaseous release) will occur prior to exceeding the Technical Specifications noted above.

The alarm setpoint values will be established using the following equation:

(SF) (ARP) (DL )

Fp ~Xg P (Wl DCFIS) where:

Page 25 of 39 Revision 7

12 PMP 6010 OSD. 001 S

P

~

SF F

P DLj the maximum setpoint of the monitor in pCi/cc for release point p, based on the most limiting organ.

an administrative operation safety factor, F 0 '

weighed 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 will be 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:

1) compute the average release rate, Q,

(or the volumetric flow rate, f ) from Bach release point p.

2) compute ZQ (or Zf ) for all release points.

3) ratio Q /ZQ (or f /Zf ) for each release point.

This rati8 iZ the MRP for that specific release point.

4) repeat

1) through

3) for each of the site's eight gaseous release points.

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 139,600 cfm for Unit 1 and 103,500 for Unxt 2.

dose rate limit to organ j in an unrestricted area (mRem/yr).

Based on continuous releases, the dose rate limits, DL-, from section 4.2.4.1, are as follows:,

jl Total. Body

~

500 mRem/year Skin

< 3000 mRem/year Any Organ

< 1500 mRem/year the annual average relative concentratipn in the applicable sector or area, in sec/m (see Attachment 3.16).

The g/Q values will be re-evaluated on an annual basis.

The re-evaluation will include determination of the worst sector.

If the new worst sector g/Q value is less than the previous year worst X/Q value, no change is required.

Page 26 of 39 Revision 7

12 PMP 6010 OSD.001 w, =

Otherwise, the Offsite Dose Calculation Manual will be modified accordingly.

(see.17) weighted factor for the radionuclide:

where C< = concentration of radionuclide i, and k has the range of all identified radionuclides in that release pathway.

For batch releases; this value may be set to one (1) for conservatism.

DCF<J

=.

dose conversion factor which is used to relate radiation dose to organ j, from exposyre to radionuclide i zn mRem/yr per

@CD/m.

See equations below.

The dose conversion factor, DCF<>, is dependent upon the organ of concern.

For the whole body:

DCF,.) = K) where:

K, =

whole body dose factor due to gamma emissions for each identified noble gas radionuclide in mRem/yr per pCi/m.

See Attachment

3. 18 For the skin:

DCF) J L) + 1. 1M) where:

L, =

1 ~ 1 skin dose factor due to beta emissions for each identified npble gas radionuclide, in mRem/yr per pCi/m.

See Attachment 3. 18 the ratio of tissue to air absorption coefficient over the energy range of photons of interest.

This ratio converts dose (mRad) to dose equivalent (mRem).

the air dose factor due to gamma emissions for each identified poble gas radionuclide in mRad/yr per pCi/m.

See Attachment 3.18.

Page 27 of 39 Revision 7

12 PMP 6010 OSD.001 For the thyroid, via inhalation:

DCF.. = P(

where:

P 1

the dose parameter, for ra'dionuclides other than noble gas, for )he inhalation pathway in mRem/yr per pCi/m.

See Attachment

3. 18 The plant vent radiation monitor low range noble gas channel setpoint, S, 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.

The thyroid dose is limited to the inhalation pathway only.

The plant: vent radiation monitor low range noble gas setpoint, Spl will be recomputed whenever gaseous releases fxom"the Containment and gas decay tanks are discharged through the plant vent to determine the most limiting organ.

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

At certain times, it may be desirable to increase the setpoint, if the vent flow rate is decreased.

This may be accomplished in one of two ways.

Max Concentration

( Ci/cc) x Hax. Flowrate (cfm)

New Hax. Concentration

()LCi/cc)

= New Max. Flow rate in cfm or Max Concentration

( Ci/cc)

~ x Hax..Flowrate.(cfm)

New Hax. FIowrate (cfm) 4 ' ' '

= New Max. Concentration in pCi/cc Waste Gas System Decay Tanks The gaseous effluents discharged from the Waste Gas System will be monitored by the vent stack monitors VRS-1505 and VRS-2505.

Due to 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 range noble gas channel (VRS-1505 or VRS-2505).

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

Page 28 of 39 Revision 7

12 PMP 6010 OSD.001 Containment Purge and Exhaust System The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust System will be monitored by the plant vent radiation monitor noble gas channels (VRS-1505 for Unit 1, VRS-2505 for Unit 2); and alarms and trip actions will occur prior to exceeding the limits in sections 4.2.2 and 4.2.4.1.

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).

The sample is then returned to Containment.

Grab sample analysis is performed for a Containment purge before release.

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.

For the Containment Pressure Relief System, no sample is routinely. taken.

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).

Steam Jet Air Ejector System (SJAE)

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 sections 4.2.2 and 4.2.4.1.

The alarm setpoint for the Condenser Air Ejector System monitor will be based on the maximum air effector exhaust flow rate, (Attachment 3.17).

The alarm setpoint value will be established using the following equations:

(SF) (MRP) (DL )

Fn

~z

$ (Vf DCFIX~

Page 29 of 39 Revision 7

12 PMP 6010 OSD.001 4 ' ' '

where:

S$ JAf the maximum setpoint, based on the most limiting organ, in pCi/cc and where the other terms are as previously defined.

Gland Seal Condenser Exhaust 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 sections 4.2.2.

and 4.2.4.1.

The alarm setpoint for the GSCE monitor will be based on the maximum condenser exhaust flow rate (1260 CFM Unit 1, 2754 CFM each for the two Unit 2 vents).

The alarm set@oint value will be established using the following equation:

(SF)(MP)(DL )

CSCR En

~Z Q

~Ws " DCFttl where:

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

Page 30 of 39 Revision 7

12 PMP 6010 OSD.001 4 ' '

6 Emergency Gaseous Setpoint Methodology Each of the routine gaseous releash paths can also indicate off-normal release concentrations.

If this would occur, the setpoint methodology for gaseous monitors would determine setpoints to alarm or trip and indicate an off-normal occurrence.

The mid and high range setpoints should be used to indicate when the effluent concentrations are possibly exceeding limits that may contribute to a dose in excess of predetermined limits as outlined in the Emergency Plan.

There are four classifications of accidents.

They are Unusual Event, Alert, Site Area Emergency and General Emergency.

The last two classifications have dose limits of 50 mRem/hr and 250 mRem/hr associated with them.

The mid and high range setpoints should be set to respond at'hese levels.

The high range setpoints for the Unit Vent monitors, VRS-1509 and VRS-2509, will use the setpoints calculated in the Radiological Support Section Calculation RS-C-0106.

The PORV monitor is a single

channel, and it is an emergency monitor.

To show when an event with radioactive releases occurred the setpoint should be set to the value for a General Emergency, 250 mRem/hr.

The equation used to determine -the setpoint is then:

s DR F +

~Z

+ DCF where:

S P

DR =

DCF the alarm/setpoint of, the monitor, pCi/cc.

the dose rate associated with the setpoint either 50 mRem/hr or 250 mRem/hr.

the maximup flow rate for this effluent point in m /sec.

To convert CFM to m /seq, multiply the flow rate in CFM by 4.71x10 The historical annual average relative concentration (sec/m3) based on meteorological data summarized in Attachment 3.16 as recommended in Regulatory Guide

1. 111 the dose conversion factor.

The conversion factor for the PORV monitors is 64,000 (Ref.

2.15).

The conversion factor for the other mid and high range monitors is 622,000 (Ref.

2. 15).

Page 31 of 39 Revision 7

12 PMP 6010 OSD.001 4.4 Radioactive Effluents Total Dose The cumulative dose contributions from liquid and gaseous effluents will be determined by summing the cumulat1ve doses as derived in Sections 4.2.3.3, 4.2.4.2 and 4.2.4.3 of this procedure.

Dose contribution from direct radiation exposure will be based on the results of the direct radiation monitoring devices located at the environmental monitoring stations.

See NUREG-0133, Section 3.8.

4;5 Radiological Environmental Monitoring Program 4.5.1 Purpose of the Radiological Environmental Monitoring Program The purpose of the REMP is to establish baseline radiation and radioactivity concentrations in the environs prior to reactor operations, to monitor critical environmental exposure

pathways, and-to determine the radiological impact, if any, caused by the operation of the Donald C.

Cook Nuclear Plant upon the local environment.

The first purpose of the Radiological Environmental Monitoring Program was completed prior to the initial operation of ezther of the two nuclear units at the Cook Plant Site.

The second and third 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. which are used are delineated in Attachment 3.19, Radiological Environmental Monitoring Program.

Included is a list of the sample media, analysis required, collection locations, and frequency requirements for both collection and analysis..19 defines the scope of the Radiological Environmental Monitoring Program for the Donald C.

Cook Nuclear Plant.

4.5.2 Conduct of the Radiological Environmental Monitoring Program Sample collection and analysis for the Radiological Environmental Monitoring Program shall be conducted in accordance with Attachment 3.19, Radiological Environmental Monitoring Program,.20, Maximum Values for Lower Limits of Detection, and Attachment 3.21, Reporting Levels for Radioactive Concentrations in Environmental Samples.

These are applicable at all times.

The on-site monitoring locations are shown on Attachment 3.22, while the off-site monitoring locations are shown on Attachment 3.23 4.5.2.1 Eachisurveillance requirement shall be performed within the specified tim'e interval in Attachment 3.19 with a maximum allowable extension not to exceed 25%

of the surveillance interval.

.4.5.2.2 If an environmental sample cannot be collected in accordance with Attachment 3.19, a description of the reasons for deviation and the actions taken to prevent a reoccurrence shall be submitted as part of the Annual Environmental Operating Report.

~age 32 of 39 Revision 7

12 PMP 6010 OSD.001 Deviations from the required samp 1ng sc e

e aVe

~

ermitted if specimens are unobtainable due to azardous cond1tions, seasonal unavailability, or to malfunction of automatic sampling equipment.

If the deviation from the required sampling schedule is due to the malfunction of "automatic sampling equipment<

~

every effort shall be made to complete the correct1ve action prior to the end of the next sampling period.

If a radionuclide is detected in any sample medium exceeding the limit established in Attachment 3.21, Reporting Levels for Radioactivity Concentrations, or if more than one radionuclide is detected in any sample medium and the Total Fractional Level (TFL),

when averaged over the calendar quarter is greater than or equal to 1, based on the following formula:

TFL =

+

+...21 C(1)

C(2)

L<2)

Where:

(1)

(2)

Concentration of 1 detected nuclide st Concentration of 2 detected nuclide nd Reporting Level of 1 nuclide from. 21 Reporting Level of 2

nuclide from nd.21 And, the activity is the result of plant effluents, then.a special report shall be subm1tted to the Commission within 30 days following the receipt of the applicable analysis results, which includes an evaluation of any release conditions, environmental factors or other aspects which may have contributed to the identified levels.

If the radioactivity was not a result of plant effluents, the results shall be described in the Annual Environmental Operating Report.

If radionuclides other than those specified in. 21 are detected and-are the result of plant effluents, this.report shall be submitted if the potential annual dose to an individual is equal to 'or greater than the calendar year limits specified in Steps 4.2.3.3.1, 4.2.4.2.1 and 4.2.4.3.1.b.

Page 33 of 39 Revision 7

12 PEP 6010 OSD.001 4.5.2.4 If a currently sampled milk farm location becomes unavailable, a special milk farm survey, for that

sector, shall be conducted within 15 days 4.5.2.4.1 If the unavailable location was an indicator farm, an alternate sample location may be established in the same sector within 8 miles of the Plant if one is available.

4.5.2.4.2 If the unavailable location was a

background

farm, an alternate sample location may be established within 20 miles of the plant "in any sector if one is available.

4.5.2.4.3 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 a special report shall be prepared and submitted to the Commission within 30 days.

Vegetation sampling shall be performed in lieu of milk sampling in that sector.

4.5.2.4.4 The provisions of Technical Specifications 3.03 and 3.04 are not.applicable.

4.5.3 Annual Land Use Census A land use census shall be conducted and shall 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 10 land covering meteorological sectors within a distance of five miles.

In lieu of the garden

census, broad leaf vegetation sampling may be performed at the site boundary in the direction sector having the highest average deposi ti on factor TDDQ value This land use census shall be conducted annually between the dates of June 1 and October 1 by door-to-door survey, aerial

survey, or by consulting local agricultural authorities.

4.5.3.1 With a land use census identifying a location(s) which yields a calculated. dose or d'ose commitment greater than the values currently being calculated in of this document, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location(s).

Page 34 of 39 Revision 7

12 PMP 6010 OSD.001 4.5.3.2 With a land use census identifying a location(s) w'hich yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent or greater than at a location from which samples are currently being obtained in accordance with section 4.5.2, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report which identifies the new location.

This new location shall be added to the Radiological Environmental Monitoring Program within 30 days, if possible.

The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring rogram after October 31 of the year in which this an6 use census was conducted.

4.5.3.3 The provisions of Technical Specifications 3.03 and 3.04 are not applicable.

4.5.4 Xnterlaboratory Comparison Program In order to comply with Regulatory Guide 4.15, the analytical vendor shall participate in both an Interlaboratory Comparison

Program, approved by the Commission for rad1oactive materials, and a plant controlled Blind Duplicate Sample Program.

Program results and identified deficiencies shall be addressed xn the Annual Environmental Operating Report.

4.5.4.1 With>> analyses not being performed as required above, report the corrective actions taken to prevent a

recurrence to the Commission in the Annual Radiological Environmental Operating Report.

4.5.4.2 The provisions of Technical Specifications 3.03 and 3.04 are not applicable.

4.6 Steam Generator Storage Facility Groundwater Radiological Monitoring Program 4.6.1 Purpose of the Steam Generator Storage Facility Groundwater Radiological Monitoring Program The purpose of the temporary on-site Steam Generator Storage Facility Radiological Monitoring Program is to. establish baseline radiological data for the groundwater surrounding the facility prior to the storage of the Unit 2 Steam Generator Lower Assemblies.

Thereafter, the purpose is to monitor the ground water through observation wells with locations as shown in Attachment 3.24, to determine the radiological impact, if any, caused by the use of the Storage Facility.

Page 35 of 39 Revision 7

12 PMP 6010 OSD.001 4.6.2 Conduct of the Steam Generator Storage Facility Groundwater Radiological Monitoring Program Groundwater samples shall be collected arid analyzed in accordance with Attachment 3.25, Steam Generator Storage Facility Radiological Monitoring Program.

The values from.20, Maximum Values for Lower Limits of Detection, and Attachment 3.21, Reporting Levels for Radioactive Concentrations in Environmental Samples shall apply.

4.7 Meteorological Model Three towers are used to determine the.meteorological conditions at Cook Nuclear Plant.

One of the towers is located at the Lake Michigan shoreline to determine the meteorological parameters assoc1ated with unmodified shoreline air.

The data is accumulated by microprocessors at the tower sites and transfeired to the central computer every 15 minutes.

The central computer uses the MIDAS program to provide atmospheric dispersion and deposition parameters.

The meteorological model used is based on guidance provided in Regulatory Guide 1.111 for routine releases.

All calculations use the Gaussian plume model.

4.8 Reporting. Requirements

~ 4.8.1 Annual Radiological Environmental Operating Report Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational

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 reports shall also include the results of the land use censuses required by Section 4.5.3. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of.21 of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The massing data shall be submitted as soon as possible in a supplementary report.

Page 36 of 39 Revision 7

12 PMP 6010 OSD.001 4 ' '

The reports shall include the following:

a summary description of the radiological environmental monitoring program 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 result of the land use census'required by Section 4.5.3; and the results of participation in the Interlaboratory Comparison Program required by section 4.5.4.

Annual Radiological Effluent Release Report Routine radioactive effluent release reports covering the operation of the unit during the previous 12 months of operation shall submitted within 90 days after January 1 of each year.

The radioactive effluent release reports shall include a

summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory 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.

The radioactive effluent release report to be submitted 90 days after January 1 of each year shall include a quarterly summary of hourly meteorological data collected during the report>.ng 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.

The report submitted 90 days after January 1

shall include an assessment of the radar.ation doses,due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year'.

These reports shall 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.

All assumptions used in making these assessments (z.e., specific activity, exposure time and i

location) shall be included in these reports.

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

The assessment of radiation doses shall be performed in accordance with this procedure.

Page 37 of 39 Revision 7

12 PMP 6010 OSD.001 The radioactive effluent-release report to be submitted 90 days after January 1 of each year shall also 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 Regulatory Guide 1.109, Rev.

1.

The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

a ~

b.

c ~

d 1 e.

Volume (cubic meters),

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

Principle radionuclides (specify whether determined by measurement.

or estimate),

Type of waste (e.g.,

spent resin, compacted dry waste, evaporator bottoms),

Type of container (e.g.,

LSA, type A, Type B, Large Quantity),

and Solidification agent (e.g.,

cement)

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluent on a quarterly basis.

The radioactive effluent release reports shall include any change to this procedure made during the reporting period.

4.9 Reporting/Management Review 4.9.1 Any changes to this procedure must be incorporated in the annual effluent report.

4.9.2 This procedure must be updated when the Radiation Monitoring System, its instruments, or the specifications of instruments are changed.

4.9.3 This procedure must be reviewed or revised as appropriate based on the results of the land use census and Environmental Radiological Monitoring Program.,

4.9.4 Any changes to this procedure must be evaluated for potential impact on other related Radiation Protection Section Procedures and changes to these procedures must be considered.

1 Page 38 of 39 Revision 7

12 PMP 6010 OSD.001 4.9.5 This procedure shall be reviewed during the first c{uarter of each year and updated if necessary.

The part of thzs procedure that shall be reviewed zs Attachment 3.16.

The review will be documented using Attachment 3.17.

5.0 Effective Date Sections 4.2 and 4.5 shall become effective when the Technical Specification submittal made per Generic Letter 89-01 are approved by the NRC.

All the other sections will be effective upon approval of the procedure.

Page 39 of 39 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 MZDE 1>>2-

-3 I>>

4>>5-6-

7-8-

9>>

10>>

11-12>>

13>>

14>>

15>>

16>>

17>>

zs-20-21-22-23-24-25-26-27-28-29-30-31>>

32-33-34-35-36-37-38-39-40-PT-1 ELEV 1

1 0

REL GND ES)

S)

PARAMETER ROUTINE REL PT SEL ( 0 NO g 1 Y

EMER.

REL PT SEL (0=NO, 1=YE WAKE SPLIT(0 Gg 1 Eg 2 SPLIT~

3=HALITSKY WAKE SPLIT SPEED SENSOR (PRI)

SPEED SENSOR (SEC)

SPEED SENSOR (FC)

DIRECTION SENSOR (PRI)

DIRECTION SENSOR (SEC)

DIRECTION SENSOR (FC)

DELTA TEMP SENSOR (PRI)

DELTA TEMP SENSOR (SEC)

DELTA TEMP SENSOR (FC)

Y STAB SEL (1=SIGTH,2=DT) 2 STAB SEL

( 1=SIGTH, 2=DT)

SIGTH/DT FAILOVER(0=NO,1=YE AMBIENT TEMP SENSOR (PRI)

AMBIENT TEMP SENSOR (SEC)

AMBIENT TEMP SENSOR (FC)

DEW POINT SENSOR (PRI)

DEW POINT SENSOR (SEC)

DELTA HT g FEET

~

FOR DT (PRI )

DELTA HT g FEET g FOR DT ( SEC)

DELTA HT ~ FEET g FOR DT

( FC)

HT / FEET g OF SPD SENS (PRI )

HT J FEET g OF SPD SENS (SEC)

HT g FEET g OF SPD SENS (FC)

REFERENCE HEIGHT (FEET)

BUILDING HEIGHT (FEET)

BUILDING WAKE COEF.(CA)

BLDG AREA FOR VIRT SOURCE STACK OR VENT HT (FEET)

TEMP CORR.

COEF.

STACK EXIT VELOCITY(M/S)

STACK OR VENT DIA(METERS)

RELEASE PT LOCATION DX g DY (METERS ) E g N SITE CENT HEAT FLUX (CAL/SEC)

SAFETY VALVE EXIT VEL(M/S)

SAFETY VALVE EXIT DZA(M)

SAFETY VALVE EXIT TEMP(F) 1 1

3 3

2 2

1 1

2 2

3 3

1 1

0 0

2 2

S) 1 1

1 1

3 3

4 4

2 2

5 5

164 164 0

0 0

0 33 33 33 33 197 197 33 33 162 0

1000 0

2000 0

0 0

0.00 0.00 0.0 0.0 0.0 0.0 PLT VENT DX DY 0

0 0.0 0.0 0.000 0.0 1

3 2

1 2

3 1

0 0

2 2

1 1

3 4

2 5

164 0

0 33 33 197 33 162 1000 2000 0

0.00 0.0 0.0 B

DX 0

1 3

2 1

2 3

1 0

0 2

2 1

1 3

4 2

5 164 0

0 33 33 197 33 0

0 0

0 0.00 0.0 0.0 DY 0

0.0 0.0

.000 0.0 REL PT-2 GND ELEV 1

1 0

1 3

2 1

2 3

1 0

0 2

2 1

1 3

4 2

5 164 0

0 33 33 197 33 162 1000 2000 0

0.00 0.0 0.0 1

3 2

1 2

3 1

0 0

2 2

1 1

3 4

2 5

164 0

0 33 33 197 33 0

0 0

0 0.00 0.0 0.0 DX DY 0

0 0.0 0.0 0.000 0.0 REL PT-3 GND ELEV 0

1 0

REL GND 4

1 3

1 2

3 1

0 0

2 2

1 1

3 4

2 5

164 0

0 33 33 33 33 162 1000 2000 0

0. 00 0.0 0.0 PT-4 ELEV 0

1 0

0 0

3 1

2 3

1 0

0 2

2 1

1 3

4 2

5 164 0

0 33 33 33 33 0

0 0

0 0.00 0.0 0.0 DX DY 0

0 0.0 0.0 0.000 0.0 Page 1 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 MZDEX 5.00 15.00 1-SPEED AT CALM(M/S) 0.3 2-Y DIFFUSION 1=SIGMA THETA,2=PASQUILL 2

3-Z DIFFUSION 1=SIGMA THETA,2=PASQUILL 2

4-SPEED EXPONENTS FOR 7 STAB.

(1) =

0. 25 (2) =

0.'25 (3) =

0. 25 (4) =

0. 33 (5)='. 50 (6) =

0. 50 (7) =

0. 50 5-DISTANCES FOR X/Q(10)

( 1)=

594.

( 2)=

2416.

( 3)=

4020.

( 4)=

5630.

( 5)=

7240.

( 6)=

12067.

( 7)=

24135.

( 8)=

40225 '

9)=

56315.

(10)=

80500.

6-DISTANCE FROM PLANT TO SITE BOUNDARY

(

1) N

=

651.

( 2) NNE=

617.

( 3) NE =

789.

( 4) ENE=

1497.

( 5) E

=

1274.

(

6) ESE=

972.

( 7) SE =

629.

( 8) SSE=

594.

( 9) S

=

594.

(10) SSW=

629.

(11) SW =

8045.

(12) WSW=

8045.

(13) W

=

8045.

(14) WNW=

8045.

(15) NW =

8045.

(16) NNW=

8045.

7-PLUME RISE SELECTOR (0=NO PLUME RISE, 1=BRXGGS JET PLUME RISE) 0 USE NO PLUME RISE FOR HALZTSKY WAKE PROCESSING 8

INDEX FOR STORING WAKE SPLIT (1/2~3'R 4) 4 9-GRAZING START (MODYHRMN) 1 1

1 0

10- GRAZING END (MODYHRMN) 123124 0

11-LIMIT(MREM) FOR PLUME DOSES (ORGANS 1-8)

~ 5.00 5.00 5.00 5.00 5.00 5.00 12-LIMIT(MREM) FOR NON-PLUME DOSES (ORGANS 1-8) 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 13-DEFAULT SPEED DAY VALUE (MPHX10) 80 14-DEFAULT SPEED NIGHT VALUE (MPHX10) 50 15-DEFAULT DIR DAY NOT USED 0

16-DEFAULT DIR NIGHT NOT USED 0

17-DEFAULT DT DAY VALUE (DEG F X10)

-10 18-DEFAULT DT NIGHT VALUE (DEG F

X 10) 0 19-DEFAULT AMB. TEMP DAY VALUE (DEG F

X 10) 520 20-,

DEFAULT AMB. TEMP NIGHT VALUE (DEG F

X 10) 380 21-PASQUXLL TABLE SPEED GP.

VS.

LAPSE GP.

LAPSE SPEED GROUP GROUP 1-5 IIZZIIIIIIXIZIIIZIXXZIIIIIXII 1 I 1

1 1

1 1 I 2 I 2

2 2

2 2 I 3

I 3

3 3

I 4

4 4

I 5 I 5

5 5

I 6

6 6

I 7 I 7

7 7

I IIIZXIXIZXI1IIXIXIXXZZIIIIZZX Page 2 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 6.000 4.000 KR85M 1.0E-07 KR90 3.0E-06 XE135 7.0E-08 FE59

5. OE-10 SR90 6.0E-12 CS137 2.0E-10 I133 1.0E-09 EM/HR) 50.00 250.00

/HR)250.00 1250.00 7.5 22.5 Page 3 of 27 Revision 7

22 WIND ROSE PERCENTS g

WINDS FROM 1 1 6 GPS /

N NNW 4.000 5.000 4.000 4.000 6.000 7.000 7.000 7.000 7.000 9.000 10.000 8.000 5.000 7.000 23-GASEOUS 10CFR20 LIMITS H3 '14 AR41 KR83M 1.0E-07 3.0E-09 1.0E-08 5.0E-05 KR85 KR87 KR88 KR89 7.0E-07 2.0E-08 9.0E-09 3.0E-06 XE131M XE133M XE133 XE135M 2.0E-06 6.0E-07 5.0E-07 4.0E-08 XE137 XE138 CR51 MN54 3.0E-06 2.0E-08 3.0E-08 1.0E-09 CO58 C060 ZN65 SR89 1.0E-09 5.0E-11 4.0E-10 2.0E-10 ZR95 SB124 CS134 CS136 4.0E-10 3.0E-10 2.0E-10 9.0E-10 BA140 NB95 I135 I131 2 'E-09 2.0E-09 6.0E-09 2.0E-10 24-LIMIT (MREM)

FOR DIFFERENT TYPES OF DOSES 1=LIQUID, TOTAL BODY

1. 50 2=LIQUID, ANY OTHER ORGAN 5.00 3=NOBLE GAS AIR.GAMMA 5.00 4=NOBLE GAS AIR BETA 10.00 5=NOBLE GAS SKIN 15.00 6=IODINE AND PARTICULATE ORGAN 7.50 7=NOBLE GAS TOTAL BODY 5.00 25-TEN DISTANCES USED FOR CLOSE-IN CALCULATIONS IN XDCAL

( 1)=

o ~

( 2)=

o ~

( 3)=

o ~

( 4)=

( 5)=

0.

( 6)=

0.

( 7)=

0.

( 8)=

0.

( 9)=

0.

(10) =

0.

26-THREE EAL LEVELS FOR WHOLE BODY GASEOUS EFFLUENTS (MR (1)

NO EMERGENCY LE 2.00 (2) ALERT'LE (3)

SITE EMERGENCY LE 250.00 (4)

GENERAL EMERGENCY GT ALL OVER GENERAL EMERGENCY 27-THREE EAL LEVELS FOR THYROID GASEOUS EFFLUENTS (MREM (1)

NO EMERGENCY LE F 00 (2)

ALERT LE (3)

SITE EMERGENCY LE 1250 F 00 (4)

GENERAL EMERGENCY GT ALL OVER GENERAL EMERGENCY 28-SEVEN LAPSE GROUPS(DEG F/100 FT)

(1)

=

-1.0424 (2)

=

-0.9333 (3)

=

-0.8230 (4)

=

-0.2740 (5)

=

0 '230 (6)

=

2.1950 (7)

=

99 '900 29-SEVEN SIGMA THETA GROUPS(DEG.)

(1)

=

2.1 (2)

=

3.8 (3)

(4)

=

12.5 (5)

=

17.5 (6)

(7)

=

60.0 30-DOSE REPORT UNITS(0 = REM/HR,

1 = MREM/HR) 1, 3 1 TEMPERATURE PROCESSING SWITCH ( 0 DEG F g 1 DEG C) 0

PMP 6010.OSD.001 ATTACHMENT 3.1 32-33-34-35-36-37-38-39-THYROID DOSE TYPE 0=ADULT DOSE FACTORS (TZD 14844) 1=CHILD DOSE FACTORS (REG 1.109) 0 PROCESS MILK THYROID OR BONE DOSE(0= MILKTHY DOSE, 1= BONE DOSE) 0 INCLUDE I132~Z134JZ135 AS KR88 IN GAMMA CALCS(0 NOg 1 YES) 1 RAD MONITOR PROMPT (0=PROMPT ALL MON.1= SELECT MONITORS) 1 RAD MON.

FLOW RATE PROMPT (0=USE DEFAULT,1=PROMPT FOR NEW RATE) 1 RAD MONITOR CORRECTION FACTOR (0 USE DEFAULTg1 PROMPT FOR NEW VALUE) 1 CONFXDENCE LEVEL PROCESSING (0=OFF,1=ON) 0 WIND SPEEDS FOR DETERMINING CONFIDENCE LEVEL SENSOR GROUND RELEASE CONFIDENCE LEVEL WIND SPEED LOW MEDIUM HIGH LESS THAN 0.00 MPH LESS THAN 0.00 MPH ALL OTHER SPEEDS SENSOR

....ELEVATED RELEASE CONFIDENCE LEVEL VALUE WIND SPEED LOW LESS THAN 0.00 MPH MEDIUM LESS THAN 0.00 MPH HIGH ALL OTHER SPEEDS 40- WIND DIRECTION (FROM)

FOR DETERMINING'ONFIDENCE'EVEL GROUND RELEASE SENSITIVE DIRECTIONS (=1)

CONFIDENCE LEVELS LOW MEDIUM N NNE ENE NE E ESE SE SSE S

SSW SW WSW W WNW NW NNW 0

0 0

0 ELEVATED RELEASE SENSITIVE DIRECTIONS (=1)

CONFIDENCE LEVELS LOW MEDIUM N NNE ENE NE E ESE SE SSE S

SSW SW WSW W WNW NW NNW 0

0 0

0 Page 4 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 41-THIS SITE USES THE LAKE BREEZE MODEL 1

(0=NONE, 1=YES) 42-PROMPTED USER IN PLUME SEGMENT MODEL FOR OPTION TO USE LAKE BREEZE MODEL(0=NO,1=YES) 1 43-WORKSPACE DRILL SCENARIO SWITCH (0=NORMAL MET DATA USED, 1=DRILL SITE(USE PERSISTENCE))

0 44-POWER LEVEL (MWTH) 0 F 00 45-TIMES OF DOME MONITOR READINGS-HRS(1-10)

O.OOE+00 0 ~ OOE+00 O.OOE+00 0.00E+00 0.00E+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 46-DOSE RATIO DOME MONITOR READZNGS-REM/HR (1-10)

O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 47-CONTAINMENT VOLUME (CU.FT)

O.OOE+00 48-REACTOR COOLANT SYSTEM VOLUME (GAL)

O.OOE+00 49-CONTAINMENT RELEASE POINT(1-4) 50- REACTOR COOLANT SYSTEM(RCS)

RELEASE POINT(1-4) 0 51-NORMAL INVENTORY RELEASE VALUE-CI/MWTH (1-8)

KR88 XE133 XE135 Z131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Z133 CS134 CS137 CE144 0.00E+00 0

OOE+00 O.OOE+00 O.OOE+00 52-NUMBER OF WIND SPIDER RINGS, 10 MILE MAP (MAX 15) 1 53-VALUE OF WIND SPXDER RINGS (MILES), 10 MILE MAP

( 1)= 10

( 2)=

0

( 3)=

0

( 4)=

0

( 5)=

0

(

6)=.

0

( 7)=

0

( 8)=

0

( 9)=

0 (10)=

0 (11)=

0 (12)=

0 (13)=

0 (14)=

0 (15)=

0 54-NUMBER OF WIND SPIDER RINGS, 50 MILE MAP (MAX 15) 1 55-VALUE OF WIND SPIDER RINGS (MILES), 50 MILE MAP

( 1)=

5

( 2)= 10

( 3)= 15

( 4)= 20

( 5)= 25

( 6)= 30

( 7)= 35

( 8)= 40

( 9)= 45 (10)= 50 (11)= 55 (12)= 60 (13)= 65 (14)= 70 (15)= 75 56 LABEL MAP SECTORS (0

NOg 1 YES) 1

'7-SIXTEEN MAP SECTOR LABELS (WINDS FROM)

( 1)N

= N

( 2)NNE= NNE

( 3)NE = NE

( 4)ENE=

ENE

( 5)E

=

E

( 6)ESE=

ESE

( 7)SE = SE

( 8)SSE=

SSE

( 9) S

=

S (10) SSW~

SSW (11) SW =

SW (12) WSW=

WSW (13)W

~

W (14)WNW= WNW (15)NW ~

NW (16)NNW= NNW 58-ACCIDENT W.BODY AND THYROID ADJUSTMENT FACTOR SWITCH (0-1) 0 59-PROMPT FOR LINE PRINTER OR TERMINAL NON-STOP PRINT 1

(0=NO, 1=YES) 60- FINITE GAMMA PLUME DOSE SWITCH FOR MODEL 4 1

(0~SECTOR AVERAGE, 1=CENTERLINE) 61-CONSIDER DURATION ZN PAG CALCULATION (0=YES,1=NO) 0 62-ENVIRONMENTAL IODINE DOSE FACTORS FOR GASEOUS EFFLUENTS 0000 (0~REGULAR, 1=ORGANIC) 63 USE EDZTTED SHORT RELEASE CLASS A CONTOUR VALUES(1 YES' NO) 0 Page 5 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3. 1 64-BETA AND GAMMA DOSE SHORT RELEASE CLASS A CONTOUR VALUES(REM/HR)

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 0 ~ OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

.THYROID DOSE SHORT RELEASE CLASS A CONTOUR VALUES(REM/HR)

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00-O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BONE DOSE SHORT RELEASE CLASS A CONTOUR VALUES(REM/HR)

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 65 - g OF HRS.

TO GO BACK FROM CURRENT TIME FOR AUTOMATIC EMERGENCY=

2 66-MULTI-PLUME PLOT SWITCH (0~

FROM SOURCE OUT,1~ THE REVERSE) 0 67 RELEASE POINTS FOR UNMONITORED RELEASE OPTION 1 0 ( GROUND/STACK) 1 g 1 68-RELEASE OPTION 10 "MONITOR" NAME FOR UNMONITORED RELEASE Field te Page 6.of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1

. -M~IDE PARAMETER NUMBER 1 PATHWAY 1

2 3

4,5 6

7 8

9 10 11 12 13 14 LIQUID PATHWAY SELECTORS BY RECEPTORS (1-5) 0= OFF 1=

ON RECEPTOR 1

1 1

0 0

0 PARAMETER NUMBER 2 LIQUID RELEASE POINT SELECTORS 0= OFF 1=

ON SELECTOR:

1 2

3 4

STATUS:

1 1

0 1

PARAMETER NUMBER 3 LIQUID ISOTOPE NAMES 1

H3 2

C14 3

NA24 4

P32 5

CR51

~

6 MN54 7

MN56 8

FE55 9

FE59 10 C058 11 C060 12 NI63 13 NI65 14 CU64 15 ZN65 16 ZN69 17 BR83 18 BR84 19 BR85 Page 7 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 RB86 RB88 RB89 SR89 SR90 SR91 SR92 Y90 Y91M Y91 Y92 Y93 ZR95 ZR97 NB95 M099 TC99M TC101 RU103 RU105 RU106 AG110M TE125M TE127M C057 TE129M TE129 SB124 SB125 TE132 I130 I131 I132 I133 I134 I135 CS134 CS136 CS137 CS138 BA139 BA140 BA141 BA142 LA140 LA142 CE141 CE143 Page 8 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 68 69 70 71 72 73 74 75 CE144 PR143 PR144 ND147 W187 NP239 UNIDEN GALPHA PARAMETER NUMBER 4 LZQ 1

12 13 16 UZD INGESTION RATES, ETC FG FRACTION OF PRODUCE FROM LOCAL GARDEN 7.600E-01 FL FRACTION OF LEAFY VEG FROM LOCAL GARDEN 1.000E+00 P AREAL SOXL DENSITY ZN PLOW LAYER (KG/M**2) 2.400E+02 RRET FRACTION OF ACTIVXTY RETAXNED ON SPRAYED VEGETATION 2.500E-01 SFMXZ SHIELDING FACTOR FOR RESIDENTIAL STRUCTURES

7. OOOE-01...,

TB PERIOD OF BUILDUP OF ACTIVITY ZN SOIL (HR) 1.310E+05 TEMLK PERIOD OF PASTURE GRASS EXPOSURE TO ACTIVITY (HR) 7.200E+02 TEVEG PERIOD OF CROP EXPOSURE TO ACTIVITY (HR) 1.440E+03 TWHLD HOLI":NG TIME IN ANIMAL DRINKING WATER POND (HR) 0.000E+00 THPA DELAY TIME FOR INGESTION OF GRASS BY ANIMALS (HR) 0 OOOE+00 THSA DELAY TIME FOR INGESTION OF STORED FEED BY ANIMALS (HR) 2.160E+03 THLM DELAY TIME FOR INGESTION OF LEAF VEG BY MAN (HR) 2.400E+01 THOM DELAY TIME FOR INGESTION OF OTHER VEG BY MAN (HR) 1.440E+03 TFMXI TRANSPORT TIME MILK-MAN (HR) 4.800E+01 TS TIME BETWEEN SLAUGHTER AND CONSUMPTION OF MEAT ANIMAL (HR) 4.800E+02 YVGRS GRASS YIELD, WET WT (KG/M**2) 7.000E-01 YVVEG OTHER VEGETATION YIELD, WET WT (KG/M**2) 2.000E+00 Page 9 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 18 19 20 21 22 23 24 25 26 27 29 31 32 33 34 35 36 37 38 39 40 DKW WEATHERING RATE CONSTANT FOR ACTIVITY ON VEGETATION (1./HR) 2.100E-03 QFC MILK COW FEED CONSUMPTION RATE (KG/DAY WET) 5.000E+01 QFG GOAT FEED CONSUMPTION RATE (KG/DAY WET) 6 OOOE+00 QFB BEEF CATTLE FEED CONSUMPTION RATE (KG/DAY WET) 5 '00E+01 QAC MILK COW WATER CONSUMPTION RATE (L/DAY) 6.000E+01 QAG GOAT WATER CONSUMPTION RATE (L/DAY) 8.000E+00 QAB BEEF CATTLE WATER CONSUMPTION RATE (L/DAY) 5.000E+01 TPMXIW ENVTL TRANSIT TIME FOR WATER INGESTION (HR)

1. 200E+01 TPMXIF ENVTL TRANSIT TIME FOR FISH INGESTION (HR) 2 400E+01 TPMXZI ENVTL TRANSIT TIME FOR INVERTEBRATE INGESTION (HR) 2.400E+01 TPMXZS ENVTL TRANSIT TIME FOR SHORE EXPOSURE (HR) 0.000E+00 USE(1,01)

WATER INGESTION (L/YR) ADULT 7.300E+02 USE(2,01)

WATER INGESTION (L/YR) TEEN 5.100E+02 USE(3,01)

WATER INGESTION (L/YR) CHILD 5.100E+02 USE(4g01)

WATER INGESTION (L/YR) INFANT 3.300E+02 USE(1,02)

SHORE EXPOSURE (HR/YR) ADULT 1.200E+01 USE(2g02)

SHORE EXPOSURE (HR/YR)

TEEN 6.700E+01 USE(3,02)

SHORE EXPOSURE (HR/YR) CHILD 1.400E+01 USE (4 g 02)

SHORE EXPOSURE (HR/YR) INFANT 0.000E+00 USE(1,03)

FRESH WATER SPORT FISH INGESTION (KG/YR) ADULT 2.100E+01 USE(2g03)

FRESH WATER SPORT FISH INGESTION (KG/YR) TEEN 1.600E+01 USE(3,03)

FRESH WATER SPORT FISH INGESTION (KG/YR) CHILD 6.900E+00 USE(4,03)

FRESH WATER SPORT FISH INGESTION (KG/YR) INFANT 0.000E+00 USE(1,04)

FRESH WATER COMMERCIAL FISH INGESTION,(KG/YR) ADULT 2.100E+01 Page 10 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 42 43 44 45 47 48 49 50 51 52 0-55 56 57 58 60 62 63 64 65 USE(2,04)

FRESH WATER COMMERCIAL FISH ZNGESTXON (KG/YR) TEEN 1.600E+01 USE(3,04)

FRESH WATER COMMERCIAL FISH INGESTION (KG/YR) CHILD 6.900E+00 USE(4;04)

FRESH WATER COMMERCIAL FISH INGESTION (KG/YR) INFANT 0.000E+00 USE(1,05)

FRESH WATER INVERTEBRATE INGESTION (KG/YR) ADULT 5.000E+00 USE(2,05)

FRESH WATER INVERTEBRATE INGESTION (KG/YR) TEEN 3.800E+00 USE(3j 05)

FRESH WATER INVERTEBRATE INGESTION (KG/YR) CHILD 1.700E+00 USE(4,05)

FRESH WATER INVERTEBRATE INGESTION (KG/YR) INFANT 0.000E+00 USE(1,06)

SALT WATER SPORT FISH INGESTION (KG/YR) ADULT 2.100E+01 USE(2,06)

SALT WATER SPORT FISH INGESTION (KG/YR) TEEN 1.600E+01 USE(3,06)

SALT WATER SPORT FISH INGESTION (KG/YR) CHILD 6 '00E+00 USE(4,06)

SALT WATER SPORT FISH INGESTION (KG/YR) INFANT 0

OOOE+00 USE(1,07)

SALT WATER COMMERCIAL FISH INGESTION (KG/YR) ADULT 2.100E+01 USE(2,07)

SALT WATER COMMERCIAL FISH INGESTION (KG/YR) TEEN 1.600E+01 USE(3,07)

SALT WATER COMMERCIAL FISH INGESTION (KG/YR) CHILD 6 900E+00 USE(4,07)

SALT WATER COMMERCIAL FISH INGESTION (KG/YR) INFANT 0.000E+00 USE(1,08)

SALT WATER XNVERTEBRATE INGESTION (KG/YR) ADULT 5.000E+00 USE(2,08)

SALT WATER INVERTEBRATE INGESTION (KG/YR) TEEN 3.800E+00 USE(3,08)

SALT WATER INVERTEBRATE INGESTION (KG/YR) CHILD 1.700E+00 USE(4,08)

SALT WATER INVERTEBRATE ZNGESTION (KG/YR) INFANT 0.000E+00 USE(1,09)

IRRIGATED LEAFY VEGETABLE INGESTION (KG/YR) ADULT 6.400E+01 USE(2,09)

XRRIGATED LEAFY VEGETABLE INGESTION'(KG/YR) TEEN 4.200E+01 USE(3,09)

IRRIGATED LEAFY VEGETABLE INGESTION (KG/YR) CHILD 2.600E+01 USE(4,09)

IRRIGATED LEAFY VEGETABLE INGESTION (KG/YR) INFANT 0.000E+00 USE(1,10)

IRRIGATED OTHER VEGETABLE INGESTION,(KG/YR) ADULT 5.200E+02 Page 11 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 66 67 68 69 70 72 73 74 75 76 77 79 80 81 82 83 84 USE(2,10)

IRRIGATED 6 '00E+02 USE(3,10)

IRRIGATED 5.200E+02 USE(4,10)

IRRIGATED 0 ~ OOOE+00 USE(1,11)

IRRIGATED 5.200E+02 USE(2,11)

IRRIGATED 6.300E+02 USE(3,11)

XRRXGATED 5.200E+02 USE(4,11)

IRRIGATED O.OOOE+00 USE(1,12)

IRRIGATED 3.100E+02 USE(2,12)

ZRRXGATED 4.000E+02 USE(3,12)

XRRIGATED 3.300E+02 USE(4,12)

IRRIGATED 3.300E+02 USE(1,13)

IRRIGATED 3.100E+02 USE(2,13)

IRRIGATED 4.000E+02 USE(3,13)

IRRIGATED 3.300E+02 USE(4,13)

IRRIGATED 3.300E+02 USE(1,14)

IRRIGATED 1.100E+02 USE(2,14)

IRRIGATED 6.500E+01 USE(3,14)

IRRIGATED 4.100E+Ol USE ( 4 ~ 14 )

IRRXGATED O.OOOE+00 OTHER VEGETABLE INGESTION (KG/YR) TEEN OTHER VEGETABLE INGESTION (KG/YR)

CHXLD OTHER VEGETABLE INGESTION (KG/YR) INFANT ROOT VEGETABLE INGESTION (KG/YR) ADULT ROOT VEGETABLE INGESTION (KG/YR) TEEN ROOT VEGETABLE INGESTION (KG/YR) CHILD ROOT VEGETABLE INGESTION (KG/YR) INFANT COW MXLK INGESTION (L/YR) ADULT COW MXLK INGESTION (L/YR) TEEN COW MILK INGESTION (L/YR) CHILD COW MILK INGESTION (L/YR) INFANT GOAT MILK INGESTION (L/YR) ADULT,.

GOAT MILK INGESTION (L/YR) TEEN GOAT MILK INGESTION (L/YR) CHILD GOAT MILK INGESTION (L/YR) ENFANT BEEF INGESTION (KG/YR) ADULT BEEF INGESTION (KG/YR) TEEN BEEF INGESTION (KG/YR)

CHXLD BEEF INGESTION (KG/YR) INFANT PARAMETER NUMBER 5 MIXING RATIOS BY RELEASE POINT (1-4)g RECEPTOR 1

1 2.60E+00 2.60E+00 1.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 AND RECEPTOR

( 1-5 )

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2 2.60E+00 2.60E+00 1.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.POE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 12 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 3

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4 2.60E+00 2.60E+00 1.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RECEPTOR 2

1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2

O.OOE+00 O.OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.00E+00 O.OOE+00 0;OOE+00- O.OOE+00 3

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0'OOE+00 O.OOE+00 4

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RECEPTOR 3

1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00.,0.00E+00

\\

2 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00'.OOE+00 4

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 RECEPTOR 4

1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RECEPTOR 5

1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 13 of 27 Revision 7

PMP 6010

~ OSD.001 ATTACHMENT 3.1.

2 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3

O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 PARAMETER 6: LIQUID EFFLUENT 10CFR20 LIMITS (MICRO-CZ/ML)

H3 P32 MN56 C058 NI65 ZN69 BR85 RB89 SR91 Y91M Y93 NB95 TC101 RU106 TE127M TE129 TE132 Z132 Z135 CS137 BA140 LA140 CE143 PR144 NP239 1.00E-03 9.00E-06 7.00E-05 2.00E-05 1.00E-04 8.00E-04 9.99E+02 9.00E-04 2.00E-05 2 ~ OOE-03 2.00E-05 3.00E-05 2 ~ OOE-03 3.00E-06 9.00E-06 4.00E-04 9.00E-06 1.00E-04 3.00E-05 1.00E-06 8

OOE-06 9.00E-06 2.00E-05 6.00E-04 2.00E-05 C14 CR51 FE55 C060 CU64 BR83 RB86 SR89 SR92 Y91

., ZR95 M099 RU103 AG110M C057 SB124 Z130 Z133 CS134 CS138 BA141 LA142 CE144 ND147 3.00E-05 5.00E-04 1.00E-04 3.00E-06 2.00E-04 9.00E-04 7.00E-06 8.00E-06 4.00E-05 8.00E-06 2.00E-05 2.00E-05 3.00E-05 6.00E-06 6.00E-05 7.00E-06 2.00E-05 7.00E-06 9.00E-07 4.00E-04 3.00E-04 1.00E-04 3.00E-06 2.00E-05 NA24 MN54 FE59 NZ63 ZN65 BR84 RB88 SR90 Y90 Y92 ZR97 TC99M RU105 TE125M TE129M SB125 Z131 Z134 CS136 BA139 BA142 CE141 PR143 W18'7 5.00E-05 3.00E-05 1.00E-05 1.00E-04 5.00E-06 4 'OE-04 4.00E-04 5.00E-07 7.00E-06 4.00E-05 9.00E-06 1.00E-03, 7.00E-05 2.00E-05 7.00E-06 3.00E-05 1.00E-06 4.00E-04 6.00E-06 2.00E-04 7.00E-04 3.00E-05 2.00E-05 3.00E-05 Page 14 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3. 1 MIDSG ALL DIRECTIONS ARE TOWARD RECEPTOR FROM RELEASE POINT GAS DOSE DIST(M)

FOR DXST(M)

FOR DIST(M)

FOR DIST(M) FOR DXST(M)

FOR GAS DOSE DIST(M)

FOR DIST(M)

FOR RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/X PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT DIRECTION 659.

8045 8045 3556.

3556.

DIRECTION 660.

814

'725.

3556.

TOWARD 0 ~

0 ~

0 0.

0.

TOWARD 0 ~

0 ~

0.

N NNE 0.

0.

0 ~

0.

0 ~

0.

0 ~

0 0 ~

0.

0 ~

0.

0 ~

0.

0 ~

0.

0 ~

0.

GAS DIST(M)

DIST (M)

DIST(M)

GAS DIST(M)

DIST(M)

DOSE FOR FOR FOR FOR

'FOR DOSE FOR FOR FOR FOR FOR RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4... MEAT, PATH-5 COW PATH 6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT DIRECTION 943.

1052.

7725.

3556.

DZRECTION 1747.

1852.

3862.

3556.

TOWARD 0

0 0.

TOWARD 0.

0.

0 ~

NE 0.

0 ~

0.

0 ~

0.

0 ~

0.

0 0 ~

0 0.

0 ~

0.

0 ~

0.

0 ~

0.

GAS DOSE DIST(M)

FOR DIST(M)

FOR GAS DOSE DIST(M)

FOR DXST(M)

FOR DIST(M)

FOR RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH~6 GOAT DIRECTION 1716

'705.

6810.

3556.

DIRECTION 1643.

1628.

2434.

3556.

TOWARD 0.

0.

TOWARD 0.

0.

ESE 0.

0.

0 ~

0.

0 ~

0.

0 ~

0.

Page 15 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3 '

GAS DOSE RECEPTOR DIST(M)

FOR PATH-1 DIST(M)

FOR PATH-3 DIST(M)

FOR PATH-4 DIST(M)

FOR PATH-5 DIST(M)

FOR PATH-6 TABLE FOR DXRECTZON TOWARD SE PLUME/GR/I '136.

0.

VEGET 914.

0.

MEAT 4354.

0.

COW 3556.

0 ~

GOAT 3556.

0.

0 ~

0.

0 ~

0.

0 ~

0.

GAS DOSE DIST(M)

FOR DIST (M)

FOR DXST (M)

FOR GAS DOSE DXST(M)

FOR DIST(M)

FOR DIST (M)

FOR GAS DOSE DIST(M)

FOR IST (M)

FOR DIST(M)

FOR GAS DOSE DIST(M)

FOR DIST(M)

FOR GAS DOSE DIST(M)

FOR DIST(M)

FOR DIST (M)

FOR DIST(M)

FOR GAS DOSE DIST(M)

FOR DIST(M)

FOR RECEPTOR TABLE FOR PATH-1 PLUME/GR/X PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR.. TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT RECEPTOR TABLE FOR PATH-1 PLUME/GR/I PATH-3 VEGET PATH-4 MEAT PATH-5 COW PATH-6 GOAT DIRECTION 1507

~

1093.

3556.

355'6.

DIRECTION 1026.

863.

6115.

3556.

DIRECTION 942.

770.

8045.

3556.

DIRECTION 8045.

8045.

DIRECTION 8045.

8045.

DIRECTION 8045.

8045.

TOWARD 0.

0.

TOWARD 0.

0.

TOWARD 0 ~

0.

TOWARD 0;

0.

0 ~

0.

TOWARD 0 ~

0.

TOWARD 0.

0.

SSE SSW SW WSW 0 ~

0 ~

0.

0 ~

0.

0 ~

0.

0..

0 ~

0.

0 ~

0.

0 ~

0.

0 ~

0.

~ 0.

0.

0 ~

0.

Page 16 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 GAS DOSE RECEPTOR TABLE FOR DIRECTION TOWARD WNW DIST(M)

FOR PATH-1 PLUME/GR/I 8045.

0.

DIST(M)

FOR PATH-3 VEGET 8045.

0.

DIST(M)

FOR PATH-4 MEAT 8045.

0.

DIST(M)

FOR PATH-5 COW 8045.

0.

DIST (M)

FOR PATH-6 GOAT 8045.

0 GAS DOSE RECEPTOR TABLE FOR DIRECTION TOWARD NW DIST(M)

FOR PATH-1 PLUME/GR/I 8045.

0.

DXST(M)

FOR PATH-3 VEGET 8045.

0.

DIST (M)

FOR PATH-4 MEAT 8045.

0.

DIST(M)

FOR PATH-5 COW 8045.

0.

DIST(M)

FOR PATH-6 GOAT 8045.

0.

0 ~

0.

0 ~

0.

0 ~

0.

0 ~

0.

0 ~

0.

GAS DOSE RECEPTOR TABLE FOR DIRECTION TOWARD DIST(M)

FOR PATH-1 PLUME/GR/I 8045.

0.

DXST(M)

FOR PATH-3 VEGET 8045.

0.

DIST(M)

FOR PATH-4 MEAT 8045.

0..

DIST(M)

FOR PATH-5 COW 8045.

0.

DIST(M)

FOR PATH-6 GOAT 8045.

0.

NNW 0.

0.

0 ~

0.

DIST.

FOR PATHWAYS 1,2, AND 7 ARE THE SAME-(RESIDENCE LOC)

Page 17 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 MIDEN DOSE FACTOR AND DISPERSION PARAMETER EDIT OPTIONS-NUREG 0133 NOTATION

[2]

[3]

(<)

(7]

NOBLE GAS TOTAL BODY DOSE FACTORS FOR GAMMA RADIATION GROUND RELEASE.

(MREM/YR PER UCI/M3)

NOBLE GAS IMMERSION SKIN DOSE FACTORS FOR BETA RADIATION (MREM/YR PER UCZ/M3)

NOBLE GAS DOSE FACTORS FOR GAMMA RADIATION ELEVATED PLUME (MRAD/YR PER UCI/SEC)

NOBLE GAS AZR DOSE FACTORS FOR GAMMA RADIATION (MRAD/YR PER UCI/M3)

INHALATZON DOSE FACTORS FOR RADIONUCLIDES OTHER THAN NOBLE GASES (MREM/YR PER UCI/M3) AND FOR FOOD AND GROUND PLANE PATHWAYS (M2*MREM/YR PER UCI/SEC)

FOR THE CRITICAL ORGAN AND MOST RESTRICTIVE AGE GROUP NOBLE GAS AIR DOSE FACTORS FOR BETA RADIATION (MRAD/YR PER UCI/M3)

INGESTION DOSE FACTORS FROM RADIOIODZNES, RADIO-ACTIVE PARTICULATES AND RADIONUCLZDES (OTHER THAN NOBLE GASES)

WITH HALF-LIVES GREATER THAN 8

DAYS (M2*MREM/YR PER UCI/SEC)

FOR THE CRITICAL ORGAN AND MOST RESTRICTIVE AGE GROUP L8]

['10 ]

ANNUAL AVERAGED RELATXVE CONCENTRATION (SEC/M3)

(ELEVATED)

ANNUAL AVERAGED RELATIVE CONCENTRATION (SEC/M3)

(GROUND)

ANNUAL AVERAGED DEPOSITION PARAMETER (1/M2)

(ELEVATED)

ANNUAL AVERAGED DEPOSITION PARAMETER (1/M2)

(GROUND)

X/Q(S)

Q(V)

'(S)

W(V)

Page 18 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 LISTING FOR K ISOTOPE VALUE AR41

, KR83M KR85M KR85 KR87 KR88 KR89 KR90 XE13 1M XE133M XE133 XE135M XE135 XE137 XE138 8.840E+03 7.560E-02 1.170E+03 1.610E+01 5.920E+03 1.470E+04 1.660E+04 1.560E+04 9.150E+01 2.510E+02 2.940E+02 3.120E+03 1.810E+03 1.420E+03.

8 '30E+03 LISTING FOR L ISOTOPE VALUE AR41 KR83M KR85M KR85 KR87 KR88 KR89 KR9 0 XE131M XE133M XE133 XE135M XE135 XE137 XE138 2.690E+03 0.000E+00 1.460E+03 1 '40E+03 9.730E+03 2.370E+03 1.010E+04 7.290E+03 4.760E+02 9.940E+02 3.060E+02 7.110E+02 1.860E+03 1.220E+04 4.130E+03 Page 19 of 27 Revision 7

PMP 6010.0SD. 001 ATTACHMENT 3.1 LISTING FOR L (NOTE:

ELEVATED RELEASES ARE NOT CONSIDERED AT COOK NUCLEAR PLANT)

DISTANCE 594.

DIRECTION (WIND FROM)

N O.OOE+00'NE O.OOE+00 NE O.OOE+00 ENE O.OOE+00 E

O.OOE+00 ESE O.OOE+00 SE O.OOE+00 SSE O.OOE+00 S

O.OOE+00 SSW O.OOE+00 SW O.OOE+00 WSW O.OOE+00 W

O.OOE+00

. WNW 0 ~ OOE+00 NW O.OOE+00 NNW O.OOE+00 2416 ~

0'.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4020.

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00,.

0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5630.

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7240.

0'.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DIRECTION 12067.

(WIND FROM) 24135.

DISTANCE 40225.

56315.

80500.

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0'.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 20 of 27 Revision 7

PMP 6010.OSD- 001 ATTACHMENT 3. 1 LISTING FOR M ISOTOPE AR4 1 KR83M KR85M KR85 KR87 KR88 KR89 KR90 XE13 1M XE133M XE133 XE135M XE135 XE137 XE138 9.300E+03 1.930E+01 1.230E+03 1 720E+01 6 '70E+03 1.520E+04 1.730E+04 1.630E+04 1.560E+02 3.270E+02 3.530E+02 3.360E+03 1.920E+03 1.510E+03 9.210E+03 LISTING FOR P PATHWAY ISOTOPE GROUND AND FOOD IIGGQATION H3 C14 CR5 1 MN54 FE59 C058 C060 ZN65 SR89 SR90 ZR95 SB124 CS134 CS136 CS137 BA140 CE141 CE144 I131 I133 I132 2.4E+03 2.4E+09 1 2E+07 1.1E+09 7 'E+08 5.9E+08 4.6E+09 2.0E+10 1.3E+10 1.2E+11 3.5E+08 0 'E+00 7.2E+10 6.1E+09 6 'E+10 2 'E+08 3.4E+07 2.0E+08 1.1E+12 9.8E+09 1.8E+06 6.5E+02 2 'E+04 1.3E+04 1.0E+06 1.0E+06 7.8E+05 4.5E+06 6.5E+05 2.0E+06 4.1E+07 1.8E+06 O.OE+00 7.0E+05 1.4E+05 6.1E+05 1.6E+06 5.2E+05 9.8E+06 1.5E+07 3.6E+06 1.7E+05 Page 21 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENTS 3.1 I134 I135 M099 NB95 SR85 6.4E+05 2.4E+07 3.2E+08 4 'E+08 O.OE+00 4.5E+04 7.0E+05 1.4E+05 4 'E+05 O.OE+00 LISTING FOR N ISOTOPE AR41 KR83M KR85M KR8 5 KR87 KR88 KR89 KR9 0 XE131M XE133M XE133 XE135M XE135 XE137 XE138 3.280E+03 2.880E+02 1.970E+03 1.950E+03 1.030E+04 2.930E+03 1.060E+04 7.830E+03 1.110E+03 1.480E+03 1.050E+03 7;390E+02 2.460E+03 1.270E+04 4.750E+03 LISTING FOR R ISOTOPE GROUND PATHWAY VEGETABLE MEAT'OW MILK'OAT.MILK,INHALATION H3 C14 CR51 MN54 FE59 CO58 C060 ZN65 SR89 SR90 ZR95 SB124 CS134 CS136 O.OE+00 O.OE+00 4.7E+06 1.4E+09 2.7E+08 3.8E+08 2.2E+10 7.SE+08 2.2E+04 O.OE+00 2.5E+08 6.0E+08 6.8E+09 1.5E+08 4.0E+03 3.5E+06 1.2E+07 9.4E+08 9.7E+08 6.1E+08 3.2E+09 2.7E+09 3.5E+10 1.4E+12 1.2E+09 3.0E+09-2.6E+10 2.2E+08 3.2E+02 5.8E+05 1.6E+06 2.2E+07 1 'E+09 3.1E+08 1.1E+09 1.0E+09 2.6E+08 1.0E+10 1.6E+09 4.7E+08 1.2E+09 4.5E+07 2.4E+03 3.2E+06 7.5E+06 3.1E+07 3.4E+08 9.1E+07 2.9E+08

1. 7E+1"0

1. 1E+10 1.0E+11 1.0E+06 7.8E+08 5.4E+10 5 'E+09 4.9E+03 3.2E+06 9.0E+05 3.7E+06 4.4E+06 1.1E+07 3.4E+07 2.1E+09 2.2E+10 2.1E+11 1.2E+05 9.3E+07 1.6E+11 1.7E+10 1.3E+03 3.6E+04 3.3E+03 7.7E+04 1.9E+05 1.1E+05 2.8E+05 1.3E+05 6.0E+05 1.1E+08 1.5E+05 4.1E+05 1.1E+06 1.9E+05 Page 22 of 27 Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.1 CS137 BA140 CE141 CE144 Z131 Z133 Z132 Z134 I135 M099 NB95 SR85

-1.0E+10-2.1E+07 1.4E+07 7.0E+07 1.7E+07 2.4E+06 1.2E+06 4.5E+05 2.5E+06 4 'E+06 1.4E+08 1.2E+05.-4E+10--

2.8E+08 5.3E+08 1.3E+10 4.8E+10 8.1E+08 7.6E+03 6.4E-03 1.4E+12 1.7E+07

. 4.7E+08 3.5E+10 1.0E+09 5.7E+07 3.2E+07 3.9E+08 5.4E+09 1.3E+02 O.OE+00 O.OE+00 6.7E-15 2.4E+05 6.8E+09 4.1E+08 4.9E+10 2.3E+08 1.5E+07 1.3E+08 1.0E+12 9.6E+09 1.4E+02 9.4E-10 2.0E+07 3.1E+08 2.9E+08 1.1E+10 1.5E+11 2.8E+07 1 'E+06 1.6E+07 1.2E+12 1.2E+10 1.6E+02 1.1E-01 2.4E+07 3.7E+07 3.5E+07 2.2E+10 8-5E+05 2.3E+05 1.3E+05 8.6E+05 1.6E+07 3.8E+06 1.1E+06 5.1E+04 7.9E+05 4.1E+02 1.0E+05 6.0E+05 LISTING FOR I/Q(S)

DISTANCE DIRECTION 594.

(WIND PROM)

N O.OOE+00 NNE O.OOE+00 NE

'.OOE+00"'NE O.OOE+00 E

O.OOE+00 ESE O.OOE+00 SE O.OOE+00 SSE O.OOE+00 S

O.OOE+00 SSW O.OOE+00 SW O.OOE+00 WSW O.OOE+00 W

O.OOE+00 WNW O.OOE+00 NW O.OOE+00 NNW O.OOE+00 2416.

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4020.

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DISTANCE 5630.

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7240 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

,O.OOE+00.

0-OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DIRECTION 12067.

(WIND FROM) 24135

~

40225.

56315.

80500.

N NNE NE ENE E

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 23 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 ESE SE SSE S

SSW SW WSW W

WNW NW NNW O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0-OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LISTING FOR X/Q(V)

DISTANCE DIRECTION (WIND FROM) 594.

2416.

4020.

5630.

7240.

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 3.66E-06 2.51E-06 3'.19E-06'.26E-06 5.66E-06 6 39E-06 8 '3E-06 9.66E-06 1.09E-05 5.17E-06 3.66E-06 2.54E-06 3 '5E-06 3.26E-06 2.64E-06 3.66E-06 4.26E-07 3.03E-07

" 3.78E-07 4.83E-07 6.18E-07 6.94E-07 9.15E-07 1.06E-06 1.26E-06 6.10E-07 4.26E-07 2.75E-07 3.57E-07 3.86E-07 3 '3E-07 4.20E-07 2.02E-07 1.46E-07 1.84E-07 2 '4E-07 3 '7E-07 3.59E-07 4.71E-07 5.45E-07 6.27E-07 2.97E-07 2.03E-07 1.32E-07 1 '1E-07 1.82E-07 1.42E-07 1.98E-07 1.21E-07 8.78E-08 1.11E-07 1.52E-07 1.99E-07 2.27E-07 2.96E-07 3.42E-07 3.87E-07 1.80E-07 1.22E-07 7.93E-08 1.03E-07 1.08E-07 8.44E-08 1.18E-07 8.47E-08 6 '9E-08 7.90E-08 1.08E-07 1.43E-07 1.64E-07 2.13E-07 2.46E-07 2.76E-07 1.28E-07 8.61E-08

.5.61E-08 7.28E-08 7.57E-08 5.91E-08 8.24E-08 DIRECTION (WIND FROM) 12067.

24135.

DISTANCE 40225.

56315.

80500.

N NNE NE ENE E

ESE 4.24E-08 3.13E-08 4.04E-08 5.59E-08 7.46E-08 8.54E-08 1.65E-08 1.24E-08 1.62E-08 2.28E-08 3.08E-08 3.54E-08 8.22E-09 6.17E-09 8.07E-09 1.15E-08 1.55E-08 1.79E-08 5.26E-09 3.96E-09 5.18E-09 7.39E-09 9.98E-09 1.15E-08 3.31E-09 2.50E-09 3.29E-09 4.75E-09 6.45E-09 7.44E-09 Page 24 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3.1 SE SSE S

SSW SW WSW W

WNW NW NNW 1.11E-07 1 28E-07 1 42E-07 6.49E-08 4 '3E-08 2.84E-08 3.68E-08 3 '9E-08 2.94E-08 4.10E-08 4.61E-08 5.28E-08 5 '7E-08 2.59E-08 1.71E-08 1.13E-08 1.46E-08 1.47E-08 1.14E-08 1.59E-08

2. 32E-08 2.66E-08 2.90E-08 1.29E-08 8.49E-09 5.64E-09 7.26E-09 7.29E-09 5.64E-09

'7.86E-09 1.50E-08 1.71E-08 1.87E-08 8.28E-09 5 '4E-09 3.62E-09 4.66E-09 4 66E-09 3.60E-09 5 '2E-09 9.66E-09 1.11E-08 1.19E-08 5 25E-09 3.44E-09 2.31E-09 2.95E-09 2.92E-09 2.25E-09 3.15E-09 LISTING FOR W ( S )

DISTANCE DIRECTION (WIND FROM) 594.

2416.

4020.

5630.

7240.

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW O.OOE+00 0

OOE+00 0 ~ OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 0

OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 0 ~ OOE+00

'O.OOE+00 O.OOE+00 O.OOE+00

'O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 0;OOE+00" O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 'OE+00 O.OOE+00 O.OOE+00 O.OOE+00.,

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DISTANCE DIRECTION 12067

'WIND PROM) 24135.

40225.

56315.

80500.

N NNE NE ENE E

ESE O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0-OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 25 of 27 Revision 7

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

OOE+00

'.OOE+00 SE SSE S

SSW SW WSW W

WNW NW NNW O.OOE+00 0

OOE+00 0

OOE+00 O.OOE+00 0

OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LISTING FOR W (V)

DISTANCE DIRECTION (WIND FROM) 594.

2416.

4020.

9.87E-10 4.32E-10 5-53E-10 5.55E-10 6 '7E-10 5-36E-10 7 '3E-10 1.06E-09 1.93E-09 1.30E-09 1.10E-09 8.74E-09 8 69E-10 8 01E-10 7 '0E-10 1.01E-09 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 2.18E-09 9.53E-09 1.22E-09 1.22E-09 1.34E-09 1.18E-09 1.62E-09 2.33E-09 4.26E-09 2.87E-09 2.42E-09 1.93E-09 1.92E-09 1.77E-09 1.68E-09 2.22E-09 2.25E-08 9.87E-09 1 26E-08 1 27E-08 1.39E-08 1 22E-08 1.67E-08 2.42E-08 4.41E-08 2 '7E-08 2.51E-08 2.00E-08 1.98E-O8 1.83E-08 1.74E-08 2.30E-08 DISTANCE DIRECTION 12067.

(WIND FROM) 24135.

40225.

1. 65E-11 7.24E-12 9.27E-12 9.30E-12 1.02E-ll 8.98E-12 1.23E-ll 4.49E-11 1.97E-11 2.52E-11 2.53E-11 2.76E-11 2.44E-11 3.34E-11 N

NNE NE ENE E

ESE SE

1. 38E-10 6 04E-11 7.74E-11 7.76E-11 8.48E-11 7.49E-11 1.02E-10 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5630.

5 ~ 18E-10 2.27E-10 2.90E-10 2.91E-10 3.18E-10 2.81E-10 3.85E-10 5.55E-10 1.01E-09 6.83E-10 5.76E-10 4 '8E-10 4.56E-10 4.20E-10 3.99E-10 5.28E-10 56315.

8 ~ 83E-12 3.86E-12 4 '5E-12 4 '6E-12 5 '3E-12 4.79E-.12 6.56E-12 PMP 6010 OSD.001 ATTACHMENT F 1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 7240..

3.30E-10 1.45E-10 1 85E-10 1.86E-10 2.03E-10 1.79E-10 2.45E-10 3.54E-10 6.46E-10 4.35E-10 3 '8E-10 2 '2E-10

2. 91E-10

~

2. 68E-10 2.55E-10 3.37E-10 80500.

4.43E-12 1.94E-12 2.48E-12 2.49E-12 2.72E-12 2.40E-12 3.29E-12 Page 26 of 27 Revision 7

PMP 6010.OSD.001 ATTACHMENT 3 '

SSE S

SSW SW WSW W

WNW NW NNW 1 '8E-10 2 70E-10 1 82E-10 1.54E-10 1 22E-10 1.21E-10 1.12E-10 1.06E-10 1 41E-10 4.82E-11 8 79E-11 5 92E-11 5.00E-11 3 98E-11 3.96E-11 3 65E-11 3.46E-11 4 58E-11 1.77E-11 3.24E-11 2 18E-11 1.84E-11 1.46E-11 1.46E-11 1.34E-11 1.27E-11 1.69E-11 9.47E-3.2 1 73E-11 1.16E-11 9.83E-12 7.82E-12 7.77E-12 7.16E-12 6.80E-12 9.00E-12 4.75E-12 8.66E-12 5.84E-12 4 '3E-12 3.92E-12 3.90E-12 3.59E-12 3.41E-12 4.52E-12 Page 27 of 27 Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.2 RAD OAC V

L U D E FLU MONITORING INSTRUMENTAT ON Instrument Minimum Channels

~eatable A

icabilit

~Actic a ~

b.

Gross Radioactivity Monitors Providing Automatic Release Termination Liquid Radwaste (1) ~

Effluent Line (RRS-1001)

Steam Generator Blowdown Line (R-19)

Steam Generator Blowdown Treatment Effluent (R-24)

At times of release At times of release At times of release 2 e Gross Radioactivity Monitors Not Providing Automatic Release Termination

'a ~

Service Water System Effluent Line (R 20, R-28)

Continuous Composite Sampler Flow Monitor Turbine Building Sump Effluent Line (1) per train At all times At all times a 0 b.

c Flow Rate Measurement Devices Liquid Radwaste Line (RFI-285)

Discharge Pipes*

Steam Generator Blowdown Treatment Effluent (DFI-352)

At times of release 4

At all times NA At times of release

Pump curves and valve settings may be utilized to estimate flow; in such

cases, Action Statement 4 is not applicable.

8 OPERABILITY of RSS-1001 includes OPERABILITY of flow switch RFS-1010, which is an attendant instrument as defined by Specification 1.6.

Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.2 TABLE NOTATION Action Action 1

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 30 days, provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Section 4.2.3.1 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.

2 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 pci/gram:

2 ~

At'east once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is >0.01 pci/gram DOSE EQUIVALENT I-131-At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when, the specific activity of the secondary coolant is <0.01 pci/gram DOSE EQUIVALENT I-131-Action Action 3

With the number of channels OPERABLE less than the required by the Minimum Ch'annels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) -at a lower limit of detection of at least 10

~ pci/ml.

4 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument CHANNEL

~CHEC SOURCE CHANNEL CHANNEL FUNCTIONAL TEST a 0 b.

co 2 ~

Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Isolation Liquid Radwaste Effluent Line (RRS-1001)

Steam Generator Blowdown Effluent Line Steam Generator Blowdown Treatment Effluent Line Gross Beta or Gamma Radioactivity Monitors Providing'Alarm But Not Isolation D*

D*

R(3)

Q(5)

Q(1)

a. Service Water System Effluent Line 3.

Continuous Composite Samplers a.

Turbine Building Sump Effluent Line N/A R(3)

N/A Q(2)

N/A 4 ~

a ~

b.

Flow Rate Monitors Liquid Radwaste Effluent Steam Generator Blowdown Treatment Line D(4)

D(4)

N/A N/A N/A N/A

During releases via this pathway Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3 '

TABLE NOTATION The CHANNEL -FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

2 0 3 ~

4 ~

Instrument indicates measured levels above the alarm/trip setpoint.

Circuit failure.*

Instrument indicates a downscale failure.*

Instrument control not set in operating mode.*

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists o

1 ~

2 ~

3 ~

Instrument indicates measured levels above the alarm setpoint.

Circuit failure.

Instrument indicate a downscale failure.

Instrument controls not set in operating mode.

(3)

(4)

The initial CHANNEL CALIBRATION shall be performed using one or more sources with traceability back to the National Bureau of Standards.

These sources shall 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.

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous,- periodic or batch releases are made.

(5)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1 ~

2 ~

3 ~

4 ~

5.

Instrument indicates measured levels above the alarm/trip setpoint.

Circuit failure.***

Instrument indicates a downscale failure.***

Instrument control not set in"operating mode.***

Loss of sample flow.

Instrument indicates, but, does not provide for automatic isolation.

- As equipment becomes operational.

- + Instrument indicates, but does not necessarily cause automatic isolation, no credit is taken for the O

automatic isolation on such occurrences.

Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTAT'ION Instrument Instrument Minimum Channels

~Oerable A licabilit Action Condenser Evacuation System a.

Noble Gas Activity Monitor (SRA-1905/2905) b.

Flow Rate Monitor (SFR-401, 2-MR-054 and/or SFR-1910/2910)

(1)

(1) 2.

3

~

5.

Unit Vent. Auxiliary Building Ventilation System a.

Noble Gas Activity (1)

Monitor (VRS-1505/2505) b.

Iodine Sampler (1)

Cartridge for VRA-1503/2503 c.

Particulate (1)

Sampler Filter for VRA-1501/2501 d.

Effluent System (1)

Flow Rate Measuring Device (VFR-315, MR-054 and/or VFR-1510/2510)

(1) e.

Sampler Flow Rate (1)

Measuring Device (VFS-1521/2521)

Containment.

Purge System a.

Aux. Building Vent.

System Noble Gas Activity Monitor (VRS-1505/2505) b.

Aux. Building Vent.. System Particulate Sampler for VRA-1501/2501 Waste Gas Holdup System a.

Noble Gas Activity Alarm and Termination of Gas Decay Tank Releases (VRS-1505/2505)

Gland Seal Exhaust a.

Noble Gas Activity Monitor (SRA-1805/2805) b.

Flow Rate Monitor (SFR-201, MR-054 or SFR-1810/2810) 5 7.

At all times

+** During releases via this pathway Page 1 of 2

. Revision 7

PMP 6010'OSD.001 ATTACHMENT 3.4 1

For pu=ge purposes only.

See Attachment 3.4 (Items 2a, 4a) and Attachment 3..5 (Items 2a, 4a) for other requirements associated with this instrument.

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

TABLE NOTATIONS Action Action Action Action 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 the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity..within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

8 With the number of channels OPERABLE less than require by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples required for weekly analysis are continuously collected with auxiliary sampling equipment as.required. in. Attachment 3.7.

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 ~

b.

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

and, 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.

Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.5 RADIOACTIV GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCERE-UIREMENT Instrument CEGQNEL SOURCE CHECK

~CHEC KDQQlEL CALIBRATION CHANNEL FUNCTIONAL TEST 1 ~

2 ~

3

~

Condenser Evacuation System a.

Noble Gas Activity D**

Monitor (SRA-1905/2905) b.

System Effluent D**

Flow Rate (SFR-401, MR-054, SRA-1910/2910)

Auxiliary Building Ventilation System a.

Noble Gas Activity D*

Monitor (VRS-1505/2505) b.

Iodine Sampler W*

(For VRS-1503/2503) c.

Particulate,.Sampler W*

(For VRS-1501/2501) d.

System Effluent D*

Flow Rate Measure-ment Device (VFR-315, (MR-054, VRS-1510/2510) e.

Sampler Flow Rate D*

Measuring Device (VFS-1521/2521)

Containment Purge System a.

Aux. Building Vent.

D**

System Noble Gas Activity Monitor (VRS-1505/2505) b.

Aux. Building Vent.

W**

System Particulate Sampler (For VRS-1501/2501)

NA NA NA NA NA NA R(2)

R(2)

NA NA R(2)

NA Q(1)

Q(1)

NA NA Q(1)

NA Page 1 of 3

Revision 7

PMP 6010 OSD 001 ATTACHMENT 3-5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVE LLANCE RE UIREMENTS Instrument CHANNEL CHECK SOURCE CHANNEL CHANNEL FUNCTIONAL TEST 4.

Waste Gas Holdup System a.

Noble Gas Activity P*

Monitor Providing Alarm 6 Termination of Gas Decay Tank Releases (VRS-1505/2505)

R(2)

Q(5) 5.

Gland Seal Exhaust a.

Noble Gas Activity (SRA-1805/2805) b.

System Eff'luent Flow Rate '(SFR-.201, MR-054, SRA-1810/2810)

D**

NA R(2)

Q(1)

At all times

- During releases via this pathway Page 2 of 3

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.5 TABLE NOTA ZONS 1)

The CKQlNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1 ~

- 2~

- 3~

- 4~

Instrument indicates measured levels above the alarm setpoint.

Circuit failure.

Instrument indicates a downscale failure.

Instrument controls not set: in operate mode.

2)

The initial CHANNEL CALIBRATXON shall be perforhed using one or more sources with traceability back to the National Bureau of Standards.

These sources shall 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.

3)

The CEBNEL CALXBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent

hydrogen, balance nitrogen, and 2.

Four volume percent: hydrogen, balance nitrogen.

4),

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volume percent

oxygen, balance nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

5)

The CHANNEL CALIBRATION TEST shall also demonstrate, that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

- 2~

- 3~

- 4

'nstrument indicates measured levels above the alarm/trip setpoint.

Circuit failure.*

Instrument indicates a downscale failure.*

Instrument controls not set in operate mode.*

Instrument indicates, but does not: provide automat:ic isolation.

As equipment becomes operational.

Page 3 of 3

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.6 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSZS PROGRAM LIQUID RELEASE TYPE

'A. Batch Waste Release Tanks'.

Plant Continuous Releases~

SAMPLING FREQUENCY Each Batch One Batch/M Each Batch Each Batch Dai,ly MINIMUM ANALYSIS FREQUENCY P

Each Batch Composite" Com osite Composite TYPE OF ACTIVITY ANALYSIS Principal Gamma Emitters' 131 Dissolved and Entrained Gases (Gamma Emitters)

H-3 Gross Alpha Sr-89, Sr-90 Fe-55 Principal Gamma Emitters'-131 LOWER LIMIT OF DETECTION (LLD)

(Wci/ml) 5x10"~

1xl0 ~

lx10 ~

lx10

~

lx10

~

Sx10-8 5x10 7

1x10 6

Grab Sample Daily Daily Compositeb Q

Composite" Dissolved and Entrained Gases (Gamma Emitters)

H-3 Gross Alpha Sr-89, Sr-90 Fe-55

""'x10

~

1x10

~

lx10 ~

Sx10-8 1x10 Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.6 TABLE NOTATION The lower limit of detection (LLD) is defined in Table Notation a. of.21.

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 re-presentative of the liquids released.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analysis, each batch shall be isolated and recirculated to ensure thorough mixing.

A continuous release is the discharge of liquid of a non-discrete volumeg e.g.

form a volume of system that has an input flow during the continuous release.

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.

Other peaks which are measurable and identifiable, together with the above

nuclides, shall also be identified and reported.

Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.7 RADZOACTZVE GASEOUS WASTE SAMPLZNG AND ANALYSZS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (pCi/ml) a a.

Waste Gas Storage Tank

b. Containment Purge

c. Condenser Evacuation System and Gland Seal Exhaust*

d. Auxi'liary Building Vent P

Each Tank Grab Samale Each Purge Grab Sampleb W

Grab Sample" Continuous Continuous Continuous Each Tank Each Purge" Mb Particulate Sample Mb M

Zodine Adsorbing/

Media Noble Gas Monitor W'odine Adsorbing/

Media Wc Particulate Sample Principal Gamma Emitters4 Principal Gamma Emitters H-3 Principle Gamma Emitter s'-3 Z-131 Noble Gases Z-131 Principal Gamma Emitters'X10~

1x10

~

1X10 1X10~

1xlQ lx10-12 lx10

~

lxlQ-12 lxlQ-11 Continuous M

Composite Particulate Sample Gross Alpha lxlQ-11 Continuous M

Composite H-3 1x10 Continuous Composite Particulate Samale Sr-89, Sr-90 lxlQ-11 Continuous Noble Gas Monitor Noble Gases 1xlQ Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.7 RADZOACTZVE GASEOUS WASTE SAMPLZNG AND ANALYSZS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limi.t of Detection (pci/ml)4 e.

Zncinerated Oil~

P Each Batch~

Principle Gamma Emitters 5 x 10"~

a 0 b.

c ~

d.

e.

g ab e Notatio The lower limit of detection (LLD) is defined in Table Notation a. of.21.

Analyses shall be also be performed following any operational occurrence which has altered the mixture of radionuclides as indicated by RCS analysis.

(i.e., start-up)

Samples shall be changed at lease once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing.

Analyses shall also be performed at.least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . for 7 days followi:ng each

shutdown, startup or similar operational occurrence which lead to significant increases or decreases in radioiodine in the Reactor Coolant System.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyzed, the corresponding LLD's may be increased by a factor of 10.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for t5e time period covered by each dose or dose rate calculation made in accordance with Sections 4.2.4.1, 4.2.4.2, and 4.2.4.3 of this document.

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, Cd-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Releases from incinerated oil are discharged through the Auxiliary Boiler System.

Releases shall be accounted for based on pre-release grab sample data.

Samples of waste oil to be incinerated shall be collected from the container in which the waste oil is stored (e.g.,

waste oil storage

tanks, 55 gal.

drums) prior 'to transfer to the Auxiliary Boiler System and shall he representative of container contents.

Page 2 of 2

. Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.8 Nulti le Releae Point Factors for Li uid Release Points onitor Descri tion SG Blowdown U1 SG Blowtfown U2 Liquid Maste Discharge Both Units onitor Number 1R-19 2R-19 RRS-1001 HRP 0.35 0.35 0.30 Page 1 of I Revision 7

PNP 6010 OSD.OOl ATTACHNENT 3. 9 SovtsCES SYSIgv LCkXX

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PMP 6010 OSD.001 ATTACHMENT 3.9 NOTES Drawings:

OP-12-5119,

-51238,

-5133, -5134, -5138,

-5138A, 5661, 5661,

-5104F.

System Descriptions:

SD-DCC-CH113,

-NE101, -HP119.

Engineering Control Procedure ECP-12-R2-08.

Drawings:

OP-12-5105,

-5105B, -5141,

-5141A, -5119, -5125, '661, 5661,

-5104F.

System Descriptions:

SD-DCC-CH114,

-NE101,

-HP119.

Drawings:

OP-12-5113,

-5119, 5661, 5661.

System Descriptions:

SD-DCC-HP102,

-HP119, NE101.

Drawings:

OP-12-5125,

-5125A, 5160.

System Descriptions:

SD-DCC-CH117.

USE THE MOST CURRENT DRAWING AND SYSTEM DESCRIPTIONS

~ Page 2 of 2 Revision 7

PLANT LI(UID EFFLUENT PARAMETERS PMP 6010 OSD.001 ATTACHMENT 3. 10 SYSTEM COMPONENTS TANKS PUMPS CAPACITY EACH FLOW RATE EACH I

Waste Dis osal S stem

+ Chemical Drain Tank

+ Laundry

& Hot Shower Tanks

+ Monitor Tanks

+ Waste Holdup Tanks

+ Waste Evapor ators

+ Waste Evaporator Condensate Tanks II Steam Generator Blowdown and Blowdown Treatment S stems 1

1 2

1 4'

2 3

2 2

600 GAL.

21,600 GAL.

25,000 GAL.

6,450 GAL.

20 GPf1 20 GPM 150 GPM 30 GPM 150 GPM

+ Star t-up Flash Tank (Vented)

+ Normal flash Tank (Not Vented)

+.Blowdown Treatment System III Essential Service Water S ste

+ Water Pumps

+ Containment Spray Heat Exchanger Outlet IV Circulatin Water Pum s

1 1

1 3 (Unit 1) 4 (Unit 2) 1,800 GAL.

350 GPM 525 GAL.

100 GPM 60 GPM 10,000 GPM 3,300 GPM 230,000 GPM*

Nominal Values Page 1 of 1

Revision 7

PMP 6010 OS'01 ATTACHMENT 3'1 OF VOLUMETRIC DETECTION EFFICIENCIES PRINCIPLE GAMMA EMITTING RADIONUCLIDES NUCLIDE I-131 Cs-137 Cs-134 Co-60 Co-58 Cr -51 Mn-54 Zn-65 Ag-110M Ba-133 Ba-140 CC<<109 Ce-139 Ce-141 Ce-144 Co-57 Cs-136 Fe-59 Sb-124 I-133

'I'-'134 I-135 Mo-99 Na-24 Nb-95 Nb-97 Rb-89 Ru-103 Ru-106 Sb-122 Sb-125 Sn-113 Sr-85 Sr-89 Sr-92 Tc-99M Y-88 Zr-95 Zr-97 Kr-85 Kr-85M Kr-88 Xe-131M Xe-133 Xe-133M Xe-135 EFFICIENCY c

m Ci cc 3.78E7 3 '

E7 7.9 E7 5 '5E7 4 '0E7 3 '0E6 3 30E7 1.58E7 9 '2E7 4.85E7 1 92E7 9.60E5 3 '7E7 1-92E8 4.82E6 3 '0E7 1.07E8 2.82E7 5.92E7 3.40E7 7.22E7 3.95E7 8.67E6 4.45E7 3 '7E7 3.50E8 5.00E7 3.47E7 1.22E7 2.55E7 3.15E7 7.32E5 3.70E7 2.87E3 3.67E7 3.60E7 5.25E7 3.37E7 3.10E7 1.56E5 3.52E7 4.10E7 8.15E5 7.77E6 5.75E6 3.82E7 Page 1 of 1 Revision 7

P~

o03.0 OSD.003.

ATTACHMEHT 3'2 eneI afar R-19 OW OW1 cpm above bkg 1.0E-QG 1.QE 05 1.0E-Q<

1.0E QG 1.0Ei02 1.0E 01 1.OE QO 1.OE-G6 1.0E-GG 1.0E-04 1.0E-Q3 1.0E-Q2 1.0E-01 1.C microcuries/mi Page 1 of 2

Revision 7

pMp 6010 OS'01 ATTACHMENT 3. 12 t BBtrnent cpm aoove bkg I.OE G6 =

'.QE>>06 =

I.OE>>04 =

~.OE~QS'=

I.QE>>02 =

I.QE>>01 I.QE>>00 I.OE-06 I.QE-OG 1.0E-04 I.QE-OS I.QE-O2 1.0E-01 I.OE>>0 microcuries/ml paqe 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.13 Offal'tOI S R-20, R-28 cpm above bkg 1.0E+06 =

1.QEi05 =

1.0E~04 =

OE~03

=

1.0E+02 =

1.0E 01

=

1.0E 00 1.0E-06 1.0E-Q5 1.0E-Q4 1.0E-03 1.0E-02 1.0E-01 1.0E+0 microcuriesiml Page 1 of 1

Revision 7

P~

6010 OSD.003.

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Revision 7

NOTES PMP 6010 OSD.001 ATTACHMENT 3.14 NOTE 1:

Drawings:

OP-12-5119,

-5123B, -5133,

-5134,

-5138, 5138A, 1-5661, 5661.

.System Descriptions:

SD-DCC-CH113,

-NE101,

-HP119.

NOTE 2:

Drawings:

OP-12-5105,

-5105B, -5141,

-5141A, -5119, 5125' 5661' 5661

'ystem Descriptions:

SD-DCC-CH114,

-NE101,

-HP119.

NOTE 3:

Drawings:

OP-12-5113,

-5119, 5661, 5661.

System Descriptions:

SD-DCC-HP102,

-HP119, NE101; NOTE 4:

Drawings:

OP-12-5125,

-5125A, 5160.

System Descriptions:

SD-DCC-CH117.

USE THE MOST CURRENT DRAWING AND SYSTEM DESCRIPTIONS Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3. 15 PLANT GASEOUS EFFLUENT PARAMETERS SYSTEM UNIT EXHAUST FLOW RATE (CFM)

CAPACXTY I

P ANT UNIT VENT:

WASTE GAS DECAY TANKS

+AUXILIARYBUILDING EXHAUST

+ENG SAFETY FEATURES VEHT

+FUEL HAHDLXHG AREA VENT SYSTEM

+CONTAINMENT PURGE SYSTEM

+CONTAINMENT PRESSURE RELIEF SYSTEM UNIT 1 UNIT 2 UNZT 1 UNZT 1 UNIT 2 UNIT l&c2 UNIT 1 UNIT 1&2 UNIT 1&2 139,600 103,500 125 72c600 64,500 25,000 30,000 12,000 1,000 4082 FT~

8100 psig (8 tanks total)

+IHSTRUMENT ROOM PURGE SYSTEM UNIT 1&c2 1,000 ZZ ccz TURBINE SEALS SYSTE UNIT 1 UNXT 2 CONDENSER A R 'EJECTOR SYSTEM NORMAL STEAM JET AXR EJECTORS UNIT l&c2 START UP STEAM JET AZR EJECTORS UNIT 1&2 230 3,600 lc260 5,508 2 Release Points-One for Each Unit 2 Release Points for Unit 2 XV START UP FLASH TANK VENT UHXT 1 UNIT 2 1,536 1,536 Page 1 of 1 Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.16 X/Q GROUND AVERAGE (sec/m~)

01JAN92 - 31DEC92 DISTANCE (METERS)

DIRECTION (WIND TO)

S SSW SW WSW W

WNW NW NNW N

NNE NE ENE E

ESE SE SSE 594.

3.75e-6 2.54e-6 4.56e-6 7.42e-6 7.33e-6 6.36e-6 9.10e-6 1.13e-5 1.04e-5 4.52e-6 3.14e-6 3.16e-6 2.44e-6 2.38e-6 2.29e-6 2.73e-6 2416.

4.41e-7 3.06e-7 5.31e-7 8.14e-7 8.16e-7 7.16e-7 9.75e-7 1.24e-6 1.19e-6 5.40e-7 3.55e-7 3.46e-7 2.69e-7 2~72e-7 2.53e-7 2.99e-7 4020.

2.06e-7 1..46e-7 2.65e-7 4.17e-.7 4.14e-7 3.60e-7 5.03e-7 6.40e-7 5.97e-7 2.61e-7 1.70e-7 1.68e-7 1.27e-7 1 ~ 27e-7 1.20e-7 1.39e-7 5630 1.21e-7

. 8.79e-.8 1.64e-7 2.62e-7 2.59e-7

.2.24e-7 3

~ 17e 7

4. 04e-7 3.70e-7 1.58e-7'.02e-7 1.02e-7 7.61e-8 7.55e-8 7.25e-8 8.19e-8 7240.

8.48e-8 6.19e-8 1.16e-7 1.88e-7 1.86e-7 1.60e-7 2.29e-7 2.91e-7 2.65e-7 l.lie-7 7.18e-8 7.25e-8 5.34e-8 5.27e-8 5.08e-8 5.73e-8 DISTANCE DIRECTION (WIND TO)

S SSW SW WSW W

WNW NW NNW N

NNE NE ENE E

ESE SE SSE 12067 4.22e-8 3.lie-8 5.94e-8 9.78e-8 9.61e-8 8.29e-8 1.20e-7 1.52e-7 1 ~ 37e-7 5.66e-8 3.61e-8 3.69e-8 2.67e-8 2.60e-8 2.53e-8 2.84e-8 24135

1. 63e-8

1. 22e-8 2.40e-8 4.03e-8 3.94e-8 3.39e-8 4.95e-8 6.30e-8 5.56e-8 2.25e-8 1.42e-8 1.47e-8 1.04e-8 1.00e-8 9.87e-9 1.09e-8 40225 8.06e-9 6.06e-9 1.21e-8 2.03e-8 1.99e-8 1.70e-8, 2.50e-8 3.19e-8 2.80e-8 1.12e-8 7.10e-9 7.38e-9 5.16e-9 4.93e-9 4.92e-9'.40e-9 56315

5. 14e-9 3.88e-9 7.78e-9 1.31e-8 1.28e-8 1.10e.-8 1.60e-8 2.06e-8 1.80e-8 7.19e-9 4.55e-9 4.74e-9 3.29e-9 3.14e-9 3.16e-9 3.45e-9 80500 3.22e-9 2.44e-9 4.97e-9 8.44e-9 8.25e-9 7.04e-9 1.04e-8 1.33e-8 1.15e-8 4.56e-9 2.88e-9 3.02e-9 2'.07e-9 1.96e-9 1.99e-9 2.16e-9 DIRECTION - SECTOR N~A NNE = B E=C ENE=D E=E ESE=

F E=G SSE

= H S

SSW SW WSW J

K L

M W = N WNW

P NW =

Q NNW = R.

Current X/Q

1. 13e-5 sec/m in Sector R

Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.16 D/Q DEPOSITION (1/m )

01JAN92 31DEC92 DISTANCE (METERS)

DIRECTION (WIND TO)

S SSW SW WSW W

WNW NW NNW N

NNE NE ENE E

ESE SE SSE 594.

2.54e-8 1.06e-8 1.41e-8 1.74e-8 2.01e-8 1.78e-8 1.69e-8 2.25e-8 3.70e-8 2.45e-8 2.37e-8 2.25e-8 1.87e-8 1.59e-8 1.46e-8 2.05e-8 2416.

2.45e-9 1.02e-9 1.36e-9 1.68e-9 1.94e-9 1.72e-9 1.63e-9 2.17e-9 3.57e-9

. 2.37e-9 2.29e-9 2.17e-9 1.80e-9 1.53e-9 1.41e-9 1.98e-9 4020.

1. 11e-9 4.62e-10 6.16e-10 7.62e-10 8.82e-10 7.78e-10 7.39e-10 9.86e-10 1.62e-9 1.07e-9 1.04e-9 9.86e>>10 8.17e-10 6.95e-10 6.39e-10 8.96e-10 5630.

5.83e-l0 2.42e-10 3.23e-10 4.00e-10 4.63e-10 4.08e-10 3.88e-10 5.17e-.10 8.50e-10 5.64e-10 5.45e-10 5.17e-10 4.29e-10 3.65e-10 3.35e-10 4.70e-10 7240.

3.72e-10 1.85e-10 2.06e-10 2.55e-10 2.95e-10 2.60e-10 2.47e-10 3.30e-10 5.42e-10 3.60e-l0 3.48e-10 3.30e-10 2.73e-10 2.33e-10 2.14e-10 3.00e-l0 DXSTANCE DIRECTION (WXND TO)

S SSW SW WSW W

WNW NW NNW N

NNE NE ENE E

ESE SE SSE 12067 1.55e-l0 6.46e-ll 8.61e-ll 1.07e-10 1.23e-10 1.09e-l0 1.03e-10 1.38e-10 2.26e-10 1.50e-10 1.45e-10 1.38e-10 1.14e-10 9.72e-ll 8.93e-ll 1.25e-10 24135 5.05e-ll 2.10e-ll 2.80e-ll 3.47e-ll 4.01e-ll 3.54e-ll 3.36e-ll 4.49e-ll 7.37e-ll 4.89e-ll 4.73e-ll 4.49e-ll 3.72e-ll 3.17e-ll 2.91e-ll 4.08e-ll 40225 1.86e-ll 7.74e-12 1.03e-ll 1.28e-ll 1.48e-ll 1.30e-ll 1.24e-ll 1.65e-ll 2 '1e 11 1.80e-ll 1.74e-ll 1.65e-ll 1.37e-ll 1.17e-ll 1.07e-ll 1.50e-ll 56315

9. 93e-12 4.13e-l2 5.5le-12 6.82e-12 7.89e-l2 6.96e-12 6.61e-12 '

8.82e-l2 1.45e-ll 9.6le-12 9.29e-12 8.82e-12 7 '1e-12 6.22e-12 5.71e-l2 8.02e-12 80500 4.98e-12 2.07e-12 2.76e-12 3.42e-12 3.96e-12 3.49e-l2 3.32e-12 4.42e-l2 7.27e-12 4.82e-12 4.66e-12 4.42e-12 3.67e-12 3.12e-12 2.87e-l2 4.02e-12 DIRECTION - SECTOR N=A NNE=B E=C ENE=D E =

E ESE ~

F E = 6 SSE = H S

SSW SW WSW J

= K L

M W=N WNW = P NW =

Q NNW = R Current D/Q 3.70E-08 1/m in Sector A

Page 2 of 2

Revision 7

PMP 6010.0SD.001 ATTACHMENT 3.17 ANNUAL EVALUATION OF g AND D VALUES FOR ALL SECTORS 1.

Received annual update of g/Q and D/Q values.

S'ignature R.P.

Department (print name, title) 2.

Worst X/Q and D/Q value and sector determined.

PMP 6010 OSD.001 has been updated.

Signature R.P.

Department (print name, title) 3 ~

Approved and verified by:

Signature R.P.

Department (print name, title)

Ret.

g25.000 Page 1 of 1

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.18 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

TOTAL BODY SKIN DOSE DOSE FACTOR FACTOR K.

L i

GAMMA AIR DOSE FACTOR M.

BETA AIR DOSE FACTOR N ~

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-. 135m Xe-135 Xe-137 Xe-138 Ar-41 (mRem/yr er C

m~

7.56E-02 1.17E+03 1.61E+01 5.92E+03 1 47E+04 1.66E+04 1.56E+04 9 '5E+01 2 51E+02 2'.94E+02 3.12E+03 1 81E+03 1.42E+03 8.83E+03 8.84E+03 (mRem/yr er Ci m~

1 '6E+03 1 34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3 06E+02 7.11E+02 1.86E+03 1 22E+04 4 13E+03 2.69E+03 (mRad/yr e

C m~

1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1 63E+04 1.56E+02 3 '7E+02 3 '3E+02 3 '6E+03 1.92E+03 1.51E+03 9.21E+03 9.30E+03 (mRad/yr er Cx m~

2 88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2 '6E+03 1.27E+04 4.75E+03 3.28E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents, from R.G.

1. 109, Table B. 1.

Page 1 of 2

Reverso.on 7

PMP 6010 OSD.001 ATTACHMENT 3.18 DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE GASEOUS'FFLUENTS*

H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu 64 Zn-65 Zn-69 Rb-86 Te-131m Te 131 Te-132 I-130

-131 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La'140 La-142 Ce-141 P

~

INHALATION PATHWAY (mRem/yr 6.47E+02 2.65E+04 1.06E+04 2.03E+06 1.28E+04 1.00E+06 7.17E+04 8 69E+04 1 02E+06 7.77E+05 4.51E+06 3.39E+05 5.01E+04 1.50E+04 6.47E+05 1 '2E+04 1 90E+05 1.99E+05 8.22E+03 3 '0E+05 1.60E+06 1 48E+07 1.69E+05 3.56E+06 4 45E+04 6.96E+05 7.03E+05 1.35E+05 6.12E+05 8.76E+02 5.10E+04 1.60E+06 4.75E+03 1.55E+03

1. 68E+05 5.95E+04 5.17E+05 P

~

FOOD

& GROUND PATHWAYS (m~

. mRem/yr er Ci sec 2.40E+03 2.38E+09 3.28E+07 1.63E+11 1.15E+07 1.14E+09 1.29E+06 1.38E+08 7.89E+08 5.89E+08 4.62E+09 3 56E+10 4.43E+OS 4 75E+06 2.01E+10 3.01E-09 2.27E+10 3.48E+07 4.18E+04 7.26E+07 8.99E+08 1 07E+12 1.79E+06 9.78E+09 6.40E+05 2.40E+07 7.21E+10 6.13E+09 6.25E+10 5.15E+05 1.52E+05 2.75E+08 5.98E+04 6.43E+04 2.77E+07 1.09E+06 3.35E+07 RADIONUCLIDE Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106

'Ag-110m Te-125m Te 127m Te-127 Te-129m Te-129 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 P

~

INHALATION PATHWAY (mRem/yr 5.57E+02 3.21E+02 2.03E+06 4.09E+07 7.34E+04 1.40E+05 2.69E+05 2.79E+03 2.45E+06 1.27E+05 1.67E+05 1.75E+06 1.40E+05 4.79E+05 1.35E+05 2.03E+03 8.44E+02 5 52E+05 4.84E+04 1.16E+07 3.67E+06 4 47E+05 1.31E+06 2.44E+04 1.68E+06 2.63E+04 1.16E+05 9.84E+06 4.33E+05 4.28E+03 3.22E+05 3.96E+04 5.95E+04 P

~

FOOD

& GROUND PATHWAYS (m-"

. mRem/yr '

74E+04 1.76E+05 1.28E+10 1.24E+11 3.41E+06

1. 11E+06 9.64E+05 1.44E+05 6.86E+06 2.59E+05 2.80E+05 3.45E+08 4.29E+06 4.06E+08 3.23E+08 2.81E+05 2.92E+04 1.5SE+08 9.12E+05 3.02E+08 1 80E+10 1.56E+08 1.06E+09 1.S3E+05 1.45E+09 3.76E+04 4.88E+06 1.95E+08 7.98E+05 2.63E+03 1.26E+07 5.90E+06 2.55E+06

If Sr-90 analysis is performed, use PE given in Ru-106-for unidentified components.

If Sr-90 and Ru-106 analyses are performed, use P. given in I-131 for unidentified components.

If Sr-90, Ru-106 and I-131 analyses are performed, use P. given in P-32 for unidentified components.

Page 2 of 2 Revision 7

PHP 6010 OSO.001 ATTACHHENT 3.19 RADIOLOGICAL ENVIROHHEHTAL HONITORING PROGRAH SAHPLE STATIONS, SAHPLE TYPES, ANO SAHPLE FREQUENCIES SAMPLE STATION 0

R PT OH OCAT OH SAHPLE

~TYP SAHPLE

~PN U

NCY ANALYSIS

~TYP ANALYSIS

~PN UEIICY OHSITE AIRBORNE AND DIRECT RADIATIOH (TLD) STATIONS OHS-1 (A"1)

ONS-2 (A"2)

OHS-3 (A-3)

OHS-4 (A-4)

ONS-5 (A-5)

ONS-6 (A-6) 1945 ft 9 1S from Plant Axis Airborne Particulate Airborne Radioiodine TLD 2338 ft 9 48 'rom Plarit Axis Airborne Particulate Airborne Radioiodine TLD 2407 ft 9 90 'ren Plant Axis Airborne Particulate Airborne Radioiodine TLO 1852 ft. 9 118 'rom Plant Axis Airborne Particulate Airborne Radioiodine TLO 1S95 ft 8 189 'rom Plant Axis Airborne Particulate Airborne Radioiodine TLO 1917 ft 9 210 'rom Plant Axis Airborne Particulate Airborne Radioiodine TLD Meekly Meekly Meekly guarterly Weekly Meekly

'Meekly guar ter ly Veekly

'Meekly

'Meekly guarterly Weekly Meekly Meekly guarterly Meekly

'Meekly Weekly Quarterly

'Meek) y

'Meekly Meekly guarterly Gross beta Gamna Isotopic 1-131 Direct Radiation Gross Seta Gamna Isotopic I-131 Direct Radiation Gross Seta Gamna Isotopic I-131 Direct Radiation Gross Seta Gamna Isotopic 1-131 Direct Radiation Grass Beta Gamna Isotopic 1-131 Direct Radiation Gross Beta Gamna Isotopic 1-131 Direct Radiation Meekly guart.

Cenp.

'Meekly Quarterly Meekly guart.

Comp.

Weekly guarterly Meekly guart.

Comp.

Meekly guarterly Weekly guart.

Comp.

'Meekly guarterly Weekly guart.

Comp.

'Meekly guarterly

'Meekly Quart.

Cenp.

Meekly guarterly ONS-7 (A-7)

ONS-8 (A-8)

ONS-9 (A-9)

OHS-10 (A-10)

ONS-11 (A-11)

ONS-12 (A-12) 2103 ft 9 36'ren Plant Axis 2208 ft 9 S2 fren Plant Axis 1368 ft 9 149'rom Plant Axis 1390 ft 9 127'rom Plant Axis 1969 ft 0 11'ram Plant Axis 2292 ft 9 63 from Plant Axis TLO TLO TLD TLO TLD TLO guarterly guarterly guarter ly guarterly guarterly guarterly Direct Radiation Direct Radiation Direct Radiation Direct Radiation Direct Radiatian Direct Radiation guarterl y guarterly Quarterly guarterly guarterly guarterly COHTROL AIRBORNE ANO DIRECT RADIATION (TLO) STATIONS HBF SBN OOW COL 16.0 miles SSV Hew Buffalo, HI 24.0 miles SE South Bend, IN 24.3 miles ENE

Oowagiac, HI 18.9 miles NNE Co'lorna, Hl Airborne Particulate

,Airborne Radioiodine TLD Airborne Par ticulate Airborne Radioiodine TLD Airborne Particulate Airbarne Radioiodine TLO Airborne Particulate Airborne Radioiodine TLO Meekly Weekly Weekly guarterly Meekly

'Meekly Weekly guarterly Meekly

'Weekly Weekly guarterly

'Meekly

'Meekly Quarterly Gross Seta Gamna Isotopic I-131 Direct Radiatian Gross Seta Gamna Isotopic 1-131 Direct Radiation Gross Beta Gamna Isotopic 1-131 Direct Radiation Gross Seta Gamna Isotopic I"131 Direct Radiation

'Meekly Quart.

Comp.

Meekly guarterly Meekly Quar t. Comp.

Weekly guarterly Meekly guart.

Cenp.

'Meekly guarterly

'Meekly guart.

Comp.

'eekly guarterly Page 1 of 4 Revision 7

PHP 6010 050.001 ATTACHMENT 3.19 RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH SAHPLE STATIONS, SAHPLE TYPES, AND SAHPLE FREQUENCIES SAHPLE HTHTTUH 0

S R PT ON OCAT ON SAHPLE

~TYP SAHPLE

~FRE U

KCY ANALYSIS TYPE ANALYSIS

~FR UEHCY OFFSITE AIRBORNE ANO DIRECT RADIATION (TLD) STATIONS OFS-1 OFS-2 OFS-3 OFS-4 OFS-5 OFS-6 OFS-7 OFS-8 OFS-9 OFS-10 OF5-11 4.5 miles NE, Pole ¹8294-44 3.6 miles, NE, Stevensville Substation 5.1 miles NE, Pole ¹8296-13 4.1 miles, E, Pole ¹8350-7Z 4.2 miles ESE, Pole ¹8387-32 4.9 miles SE, Pole ¹8426-70 2.5 miles S, Bridgman Substation 4.0 miles 5, Pole ¹84Z4-20 4 '

miles ESE. Pole ¹8369"214 3.8 miles S, Pole ¹842Z-152 3.8 miles S, Pole ¹8423-12 TLO TLD TLD TLD TLD TLO TLD TLD TLO TLD TLO guarterly guarterly guarterly guarterly guarterly guarterly guarter ly guarterly guarterly guarterly guarter ly Direct Radiation guarterly Direct Radiation Quarterly Direct Radiation guarterly Direct Radiation Quarterly Direct Radiation guarterly Direct Radiation guarterly Direct Radiation guarterly Direct Radiation guarterly Direct Radiation guarter ly Direct Radiation guarterly Direct Radiation guarter ly GROUNOMATER (MELL MATER) SAHPLE STATIONS

'M-2 M-3 M-6 M-7 M-8 M-9 M-10 M"11

'M-12 M-13 OR INKIPNG 'MATER STJ 1969 ft 9 11'rom Plant Axis Groundwater 2292 ft 9 63 'rom Plant Axis Groundwater 3279 ft 9 107 from Plant Axis Groundwater 418 ft 9 301'rom Plant Axis Groundwater 404 ft 9 290 'rom Plant Axis Groundwater 424 ft 8 273 'rom Plant Axis Groundwater 1895 ft 9 189 'rom Plant Axis Groundwater 1208 ft 9 48'rom Plant Axis Groundwater 1523 ft 9 22 'rom Plant Axis Groundwater, 4305 ft 9 133 'rom Plant Axis Groundwater 3308 ft 8 157 'rom Plant Axis Groundwater 2678 ft 0 168'rom Plant Axis Groundwater 2153 ft 9 189 'rom Plant Axis Groundwater St. Joseph Public Intake Sta.

Drinking water 9 mi.NE Lake Twp. Public Intake Sta.

Orinkin9 water 0.4 mi.S guarterly guarterly guarterly guarterly guarterly guarterly guarterly guarterly Quarterly guarterly guarter ly guarter1y guarterly Daily Daily Gamna Isotopic Tritium Gamrra Isotopic Tritium Gamrra Isotopic Tritium Gamrra Isotopic Tritium Gamrra Isotopic Tritium Gamrra Isotopic Tritium Ganma Isotopic Tritium Gamrra Isotopic Tr itium Gamna Isotopic Tr'itium Gamna isotopic Tritium Gamna Isotopic Tr itium Gamrra Isotopic Tritium Gamrra Isotopic Tritium Gross Beta Gamna Isotopic 1-131 Tritium Gross Beta Gamna Isotopic 1-131 Tritium guarterly guarterly guarterly guarterly guarterly guarterly guarterly guarterly Quarterly guarterly guarter ly guarterly guarterly guarterly guarterly Quarterly guarterly Quarterly guarter ly guarterly guarterly guarterly Quarterly guarterly guarter ly guarterly 14 day Comp.

14 day Comp.

guart.

Comp.

14 day Comp.

guart.

Comp.

Page 2 of 4 Revision 7

PHP 6010 OSD.001 ATTACMHENT 3. 19 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM SAHPLE STATIONS, SAHPLE TYPES, AND SAMPLE FREQUENCIES SAHPLE

~STAT ON 0 SCRIPTION LOCATION SAHPLE TYPE SAHPLE ANALYSIS

~FR UENCY ANALYSIS

~FIIE UENCY SURFACE

'WATER Ll LZ L3 L4 L5 Condenser Circulating Water Surface Intake Plant Site Boundary - South Surface 0.3 mi. south of Plant Centerline Plant Mite Boundary - North Surface 0.2 mi. north of Plant Centerline Shoreline 0.1 mi. South of Surface Plant Intakes Shoreline 0.1 mi. North of Surface Plant Intakes Water Daily Water Daily Water Daily Water Daily Water Daily Ganma Isotopic Tritium Gaama Isotopic Tritium Gamna Isotopic Tritium Ganma Isotopic Tritium Ganma Isotopic Tritium Honth.

Comp.

Quart.

Comp.

Honth.

Comp.

Quart.

Comp.

Honth.

Comp.

Quart.

Comp.

Honth.

Comp.

Quart.

Comp.

Month.

Comp.

Quart.

Comp.

SEDIHEHT L2 L3 L4 LS Plant Site Boundary - South Sediment 0.3 mi. south of Plant Centerline Plant Site Boundary - North Sediment 0.2 mi. north of Plant Centerline Shoreline 0.1 mi South of Sediment Plant Intakes Shoreline 0.1 mi North of Sediment Plant Intakes Semi-Ann.

Semi-Ann.

GaEtma Isotopic Semi-Annual.

Ganma Isotopic Semi-Annual.

Gasma Isotopic Semi-Annual.

INGESTION - HILK Indicator Farms Totzke Farm Schuler Farm

'Warmbein Farm 5.1 miles ENE, Baroda 4.1 miles SE, Baroda 7.7 mi. 5, Three Oaks Freehling Farm 7.0 mi. SE, Buchanan Hi 1k Hilk Hi1k Hi1k Once every 15 days Once every 15 days Once every 15 days Once every 15 days I"131 Ganma Isotopic 1-131 Ganma Isotopic 1-131 GaEtma Isotopi c I-131 Ganma Isotopic per sample per sample per sample per sample per sample per sample per sample per sample INGESTION - HILK

Background

Farms Livinghouse Farm 20 miles S, La Porte, IN Hilk Wyant Farm 20.7 miles E, Oowagiac Hi1k Once every 15 days Once every 15 days 1-131 per sample Ganna Isotopic per sample I-131 per sample Gamna Isotopic per sample INGESTION - FISH ONS-N ONS-S OFS-N OFS-S 0.3 nile N, Lake Hichigan 0.4 mile S, Lake Hichigan 3.5 mile N, Lake Hichigan 5.0 mile 5, Lake Michigan Fish Fish Fish Fish 2/year.

Z/year.

2/year.

GaEntEa Isotopic Gamna Isotopic Gamna Isotopic Game Isotopic per sample per sample per sample per sample Page 3 of 4 Revision 7

PMP 6010 050.001 ATTACHHENT 3. 19 RAOIOLOGICAL ENVIRONMENTAL HONITORING PROGRAH SAMPLE STATIONS, SAHPLE TYPES, ANO SAHPLE FREQUENCIES SAHPLE STAT!UP R

PT ON LOCAT ON SAMPLE

~TYP SAHPLE

~TU UUUCY ANALYSIS

~TYP ANALYSIS

~PU U

UCY INGESTION - FOOO PROOOCTS Off Site In a land sector containing grapes, approximately 20 miles from the

plant, and 180 degrees fram the sector with the highest 0/Q.

On Site Nearest sample to Plant in the highest 0/Q land sector.

Grapes Broad leaf vegetation Grapes At time. of,... '.. Gasnta Isotopic; At time of harvest harvest At time of Gannta Isotopic At time of harvest harvest At time of Gamna Isotopic At time of

~ harvest harvest Composite samples of Orinking and Surface water shall be collected at least daily. Particulate sample filters should be analyzed 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, gatnna isotopic analysis should be performed on the individual samples.

If at least three indicator milk samples and one background milk sample cannot be obtained, then three indicator broad leaf samples will be collected at different locations, within eight miles of the plant, in the land sector with the highest 0/Q (refers to the highest annual average 0/Q).

Also one background broad leaf sample will be collected approximately twenty miles from the plant in a land sector 180 degrees from the land sector with the highest 0/Q.

Please note the following definitions:

Meekly -> at least once per every seven (7) days Honthly -> at least once per every thirty-one (31) days Quarterly

> at least once per every ninety-two (92) days Semi-annually

> at least once every one hundred eight-four (184) days Page 4 of 4 Revision 7

PMP 6010 OSD.001 ATTACHMENT 3 ~ 20 V

UES FOR THE LOWER L S

OF DETEC IO Gross Beta Food Product Water Milk pC)~

~Ci 1

Air Filter Fish Sediment

~C~m3 0.01 Ci K wet Ci K d

H-3 Ba-140 La-140 Cs-134 Cs-137 Zr-95 Nb-95 Mn-54 Fe-59 Zn-65 Co-58 Co-60 I-131 60 60 60 2000 60 15 15 18 30 15 15 30 30 15

.15 60 60 15 15 18 0.06 0.06 0.07 130 150 130 260 260 130 130 150 180

" LLD for drinking "water Page 1 of 2

Revision 7

PMP 6010 OS'01 ATTACHMENT 3.20 NOTES P

The Lower Limit of Detection (ILD) is. defined as the smallest.

concentration of radioactive material in sample that willbe detected with 954 probability and 54 probability of falsely concluding that; a blank observation represents a "real" signal.

I For a particular measurement system (which may include radiochemical separation),

the 1LD is given by the equation:

II 4 '6 x S Zx Vx2.22x Yx e'here LLD is the ~ariori lower limit of detection as defined above as pCi per unit mass or volume.

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

The value of S used in the calculation of the LLD for

the detection system shall be based on the actual observed variance of the background counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Zn calculating the LLD for a radionuclide determined by gamma-ray spectroscopy, the background shall include the typical contributions of other radionuclides normally present in the samples (i. e.

K-40 in milk samples).

I Analy'sis performed in such a manner that the stated LLDs will, be achieved under routine conditions.

Occasionally background It fluctuations, unavoidably small sample sizes, the presence of'nterfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable.

Zn such

cases, the contributing factors will be identified and describes in the Annual Radiological Environmental Operating Report.

E is the counting efficiency of the detection equipment as counts ger transformation (i. e. disintegration)

V is the sample size in appropriate mass or volume units 2.22 is the conversion factor from picoCuries (pCi) to transf ormations (disintegrations) per minute Y is the fractional radiochemical yield as appropriate is the radioactive decay constant for, the, particular radionuclide

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

B.

The LLDs given in ATTACHMENT 3.21 are for drinking water.

C.

Other peaks which are measurable and identifiable, together with the radionuclides listed in ATTACHMENT 3.21, shall be identified and reported.

Page 2 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.21 REPOR NG LEVELS FOR IOACTIV CONCENTRAT ON I

ENVIRONMENT SAMPLES H-3 Ba-140 La-140 Cs-134 Cs-137 Zr-95 Nb-95 Mn-54 Fe-59 Zn-65 Co-58 Co-60 I-131 Food Product 1000 2000 100 30 50 400 400 1000 400 300 300 1000 60 70 Water Milk

~C-),

~Ci 20000 200 300 200 300 Air Filter

~c1 m~

10.00 20 00 0.90 Fish Ci K wet 1000 2000 30000 10000 20000 10000 30000 Page-1 of 1

Revision 7

PMP 6010 OSD 001 ATTACHMENT 3.22

'PLANT" SITE TLD, AIR AND WATER SAMPLING STATIONS.

~t TN AHL MICHIGAN = L5 L1 NR i A~

UN8 ESTRlCTKD Ag gP PROPERT USE R ARBOR TRLCIC SHORELINE

'~ Rf PLED l

765 N REIPElaE aaao aa, A Air, TLDStatxons W

Well Water Sample Stations L

Lake Water Sample Stations NOT Stations A7 through A12 are TLD Stations only Station L2, L3, L4 and L5 are also sediment sample stations.

Page 1 of 1 Revision 7

PMP 6010 OSD. 001 ATTACHMENT 3. 23 TLD Stations Nithin 1 5 Mile Radius of Plant

~ g u.

Ct5 5

f Page 1 of 2

Revision 7

PMP 6010 OSD.001 ATTACHMENT 3.23 TLD, Air, Intake and Milk Sample Stations within 20 miles of Cook Plant M Milk Sample Stations L Lake Water Sample Station (Intakes)

(

c KHTQN HAH 0 C CGA ah J

QQMQ IICRSQL 10 g~~ QF Ml~

Page 2 of 2

Revision 7

STEAM GENERATOR STORAGE FACILITY MONITORING WELLS j4$ kv

'illb

,O gyghg ggHKRAT0ll

~ SgOehnS VhCll.ill I

ygyiigg ST@~ loggg8h'Plll

~n'oaaCE Vh4il l><

GAGA-l o

IID 0

COU M ~

~ 0 M 0 Monitoring Wells Monitoring Well MSGR-3 Was Not Drilled

PHP 6010 OS0.001 ATTACHHENT 3.25 STEAH GENERATOR STORAGE FACILITY RADIOLOGICAL HONITORING PROGRAH SAMPLE STATIONS, SAHPLE TYPES, AMD SAHPLE FREQUENCIES SAHPLE ETRTIDR DESCRIPTIOM LOCATION SAMPLE TYPE SAHPLE ANALYSIS

~FIIEDtt IICY

~TYP ANALYSIS

~FR DD RCY SGRP-1 0.8 m( 0 95'rom Plant Axis Grounduater Quarterly Gross Alpha Gross Beta Gamna Isotopic Quarterly Quarterly Quarterly SGRP-2 0.7 mi 0 92'rom Plant Axis Grourxtuater'uarterl'y Gross Alpha""" " 'uarterly Gross Beta Quarterly Gaama Isotopic Quarterly SGRP-4 0.7 mi 0 93'rom Plant Axis Groundwater Qbarterly Gross Alpha Gross Beta Gamna Isotopic Quarterly Quarterly Quarterly sGRP-5 0.7 mi 0 92'rom Plant Axis Groundwater Quarterly Gross Alpha Gross Beta Gaema Isotopic Quarterly Quarterly Quarterly Page 1 of 1

Revision 7

ML17332A249

Text

M W = N WNW

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