ML20035D107
| ML20035D107 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/07/1992 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20035D106 | List: |
| References | |
| PROC-921207, NUDOCS 9304120148 | |
| Download: ML20035D107 (64) | |
Text
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DPP 5.4.2 ISSUE 1
.Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 64 ServlCO' PUBUC SERVICE COMPANY OF COLORADO 1
4 1h OFFSITE DOSE CALCULATION MANUAL (ODCM) i i
i Approved ger:
V Z{7!f?
Date:
Facility Sugp6rt Manager 3
!7!Y Approved:
Date:
Pro 3ect Assurance Manager e
Approved:
/2/7/92--
Date:
Operations Manageg;V
)
i Approved:
[
Date:
k q
Engineering Manager DSRC.TC13 Reviewed:
12 07-92 Date:
DSRC Meeting NumDer I
i Reviewed:
A h Date:
l ISRC Meeting Number 1
i 4
930412014g 930406 4
yDR ADOCK 05000267 PDR Fonucos m.zz. m
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DPP 5.4 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 peg 3 2'of 64 SerVICO*
PUBLIC SERVICE COMPANY OF COLORADO TABLE OF CONTENTS Pace 1.0 PURPOSE 3
1 2.0 APPLICABILITY 4
3.0 GENERAL.........................
4
4.0 REFERENCES
6 5.0 ATTACHMENTS.......................
7 6.0 PROCEDURE.
8 6.1 Licuid Effluent Release Recuirements 8
6.2 Licuid Effluent Surveillance Recuirements.
10 6.3 Licuid Effluent Comoliance with 10CFR20 11 6.4 Licuid Effluent Doses - Comoliance with 10CFR50 13 6.5 Licuid Effluent Releases - Comoliance with Tritium Discharce Understanding.
15 6.6 Licuid Effluent Monitor Alarm Setooint Determination:
Continuous Releases 18 6.7 Licuid Effluent Monitor Alarm Setnoint Determination:
Batch Releases 19 6.8 Gaseous Effluent Generic Release Recuirements 20 6.9 Gaseous Effluent Batch Release Recuirements 21 6.10 Gaseous Effluent Surveillance Recuirements 22 6.11 Gaseous Effluent Dose Rate - Conoliance with 10CFR2O 23 i
6.12 Gaseous Effluents - Comoliance with 10CFR50 l
25 6.13 INFORMATION RELATED TO 40CFR190 AND 40CFR141 27 6.14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM......................
29 7.0 REPORTING REOUIREMENTS 31 1
FORM (01 T72 22 - 3643
4 r
DPP 5.4.2 ISSUE 1 l
Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 64 l
Service
- PUBUC SERVICE COMPANY OF COLORADO i
1.0 PURPOSE l
i 1.1 The Offsite Dose Calculation Manual (ODCM) is a f
I supporting document of the Fort St. Vrain Nuclear l
Station Decommissioning Technical Specifications.
The
}
ODCM describes the methodology and parameters to be i.
used in calculation of offsite doses due to radioactive gaseous and liquid effluents.
This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints.
Liquid and gaseous radioactive waste treatment system configurations are described in the Decommissioning Plan (Ref. 4.1).
4 1.2 This ODCM provides the information and methodologies to be used by Fort St. Vrain (FSV) to assure compliance with 10CFR20, 10CFR50.36a, 10CFR50 Appendix A (GDC 60 &
1 64), 10CFR50 Appendix I, and 40CFR190 with respect to liquid and gaseous radiological effluents.
1.3 This ODCM is based on " Radiological Effluent Technical 4
Specifications for PWR's (NUREG-0472, Draft)," and follows the methodology and models suggested by NUREG-i 0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," and other inputs from the Nuclear Regulatory Commission (NRC).
i j
Regulatory Guide 1.109 is used for guidance and ICRP-30 dose conversion factors are used for dose calculations.
4 l
1.4 This ODCM is maintained at Fort St. Vrain for use as a reference guide and training document of accepted j
methodologies and calculations.
Changes in the calculation methods or parameters will be incorporated to ensure this ODCM represents the present methodology j
in all applicable areas.
Changes to this ODCM will be J
reviewed and approved in accordance with Section 5.10, i
Fort St. Vrain Decommissioning Technical i
Specifications.
1.5 Also included in this manual is a description of the FSV Radiological Environmental Monitoring Program (REMP) in Attachment F.
This designates specific sample types and locations currently used to comply l
with FSV Decommissioning Technical Specification requirements for the REMP.
They are subject to change based on the results of the annual land use census.
i i
1 FORM (Da372 22 3M3 i
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i DPP 5.4 2 0 SerVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING JTATION Page 4 o 64 PUBLIC SERVICE COMPANY OF COLORADO l
2.0 APPLICABILITY This procedure is applicable to all routine, planned liquid and gaseous effluent releases made pursuant to the FSV Decommissioning Technical Specifications and unplanned liquid and gaseous effluent releases.
3.0 GENERAL 3.1 The Radiation Protection Manager (RPM) shall be responsible to assure that the ODCM is utilized in accordance with the FSV Decommissioning Technical Specifications.
The RPM is also responsible for ensuring that all radioactive waste is handled, stored, and disposed of in accordance with NRC requirements and FSV procedures.
3.2 All radioactive liquid waste is discharged via a common line, is monitored by a liquid waste activity monitor, and therefore, there are no multiple release points and monitor settings do not have to be reducLd to account for multiple releases.
3.3 Liquid effluent monitor alarm setpoints are determined in order to assure compliance with 10CFR20.
The setpoints ensure that the concentration of radionuclides in the liquid effluent at the site boundary (unrestricted area) does not exceed the concentrations specified in 10CFR20, Appendix B.
3.4 If the calculated alarm setpoint for any of the FSV radiation monitors exceeds the range of the instrument, appropriate lower setpoints will be determined by the RPM.
In all cases, since the setpoint is reduced, compliance with the limits in this procedure will be i
assured.
3.5 The alarm setpoints as calculated in this procedure are the maximum allowable; setpoints may be set lower than i
the calculated values if so desired.
3.6 Surveillance requirements must be completed within +25%
of the specified frequency.
Should this frequency be exceeded, the applicable instrument shall be declared i
inoperable until such time that the required test or calibration is successfully performed.
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l FORM (D)T/2 22 3643 l
e DPP 5.4.2 ISSUE 1 0 $9fVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 64 PUBUC SERVICE COMPANY OF COLORADO i
3.7 The appropriate portions of the liquid and gaseous effluent treatment systems shall be used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines l
for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.
3.8 The LLD is defined for purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
3.9 For a particular measurement system which may include radiochemical separation:
i LLD=
2.71+4.66/E T Eib2. 22E6*Y exp (- A A C)
Where:
LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, VB is the standard deviation of the total background counts or of the total counts of a i
blank sample, as appropriate, as counts, T is the count time of background in minutes, E is the counting efficiency as counts per disintegration or counts per gamma for gamma i
spectroscopy, i
V is the sample size in units of mass or
{
- volume, i
t 4
2.22E6 is the number of disintegrations per j
minute per microcurie, (dpm/ Ci),
2 Y is the fractional radiochemical yield when l
applicable and/or the gammas per
]
disintegration when applied to gamma i
spectroscopy, i
i I
I FORM (D)T72-22 24 i
DPP 5.4 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1
$9fVICO*
PUBLIC SERVICE COMPANY OF COLORADO Page 6 of 64 f
1 A is, if radioactive decay correction is applicable, the radioactive decay constant for the particular radionuclide, At is the elapsed time between the sample collection and time of counting.
3.10 Values of E, V,
Y, and At, which are appropriate to the sample, should be used in the calculation.
3.11 It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
4.0 REFERENCES
4.1 FSV Decommissioning Plan 1
1 4.2 10CFR20, " Standards for Protection Against Radiation" 4.3 Regulatory Guide 1.109, " Calculation of Annual Doses to l
Man from Routine Releases of Reactor Effluents for the
?
Purpose of Evaluating Compliance with 10CFR50, I," October, 1977 Appendix 4.4 10CFR50, " Domestic Licensing of Production and t
Utilization Facilities"
)
4.5 NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
October, 1978 4.6 40CFR190, " Environmental Radiation Protection Standards 2
for Nuclear Operation" 1
4.7 40CFR141, " EPA Interim Drinking Water Standards for Radionuclides" 4.8 Decommissioning Technical Specifications 4.9 ICRP-30, " Limits for Intakes of Radionuclides by Workers" 4.10 ORNL-4992, "A Methodology for Calculating Radiation i
Doses from Radioactivity Released to the Environment" i
FORM (D)372 3643
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DPP 5.4.2 ISSUE 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 64 SGIVlCO*
PUBLIC SERVICE COMPANY OF COLORADO 4.11 NUREG/CR-4007, " Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements" 4.12 USNRC Regulatory Guide 4.16, " Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication Plants and Uranium 4
Hexaflouride Production Plants", December, 1985 1
4.13 USNRC Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", June, 1974 4.14 USNRC Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants", September, 1980-4.15 USNRC Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors" 4.16 USNRC Regulatory Guide 1.145, " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" 4.17 NUREG-0472 (DRAFT), " Radiological Effluent Technical Specifications for PWR'S" 4.18 Tritium Discharge Understanding between Public Service Co. of Colorado and the Colorado Department of Health, Water Quality Control Division, August, 1992 5.0 ATTACHMENTS 5.1 DPP 5.4.2-A Ag Values (Dose Factors) for Fort St.
Vrain.
5.2 DPP 5.4.2-B P, Values for FSV.
)
5.3 DPP 5.4.2-C R Values for FSV.
5.4 DPP 5.4.2-D Monthly South Platte River Low Flow Rates.
f 5.5 DPP 5.4.2-E ODCM Background Information.
5.6 DPP 5.4.2-F Radiological Environmental Monitoring Program.
FORM 108772-22 3M3
i DPP 5.4.2 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 64
$9fVICe*
PUBUC SERVICE COMPANY OF COLORADO 2
l 6.0 PROCEDURE 6.1 Licuid Effluent Release Reauirements 6.1.1 The maximum instantaneous release rate of radioactive liquid effluents from the site shall be such that the concentration of radionuclides in the unrestricted area does not exceed the values specified in 10CFR20.
If plant conditions exist such that the concentration of radioactivity in the liquid effluent from the plant exceeds the specified limits, immediate action shall be taken to 4
terminate the release.
6.1.2 Liquid effluent releases will also be controlled so that the EPA Safe Drinking Water Standard of 20,000 pCi/t for tritium will n'ot be exceeded in the South Platte River on a monthly average basis.
This is in accordance with the Tritium Discharge Understanding between PSC and the Colorado Department of Health.
6.1.3 Prior to initiating a batch or continuous f
release, a sample of liquid to be released via the radioactive liquid effluent discharge pathway shall be analyzed for principal gamma t
emitters, tritium, and for other radioisotopes of concern as identified by previous experience.
The results of these analyses shall be used to ensure that the concentrations at the point of release to the unrestricted area are maintained within the limits described in 6.1.1 and 6.1.2 above.
6.1.4 The lower limits of detection (LLD) for the radioactive liquid waste sampling and analysis program shall satisfy the following:
Principal Gamma Emitters SE-7 pCi/mt H-3 1E-5 pCi/nf i
i J
1 t
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+
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DPP 5.4.2 ISSUE 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 64 SOfVICO*
PUBUC SERVICE COMPANY OF COLORADO i
6.1.5 The principal gamma emitters for which the LLD specification applies are the following i
radionuclides:
Mn-54, Co-60, 2n-65, Cs-134, l
Cs-137, and Ce-144.
This list does not mean that only these nuclides are to be considered.
Other reactor produced gamma emitters that are identified shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
6.1.6 Continuous and batch effluent discharges shall not occur simultaneously.
6.1.7 All liquid effluent releases shall be continuously monitored by a gamma activity monitor and its associated recorder.
6.1.8 Equipment shall be operable to automatically terminate the release on high gamma activity or low blowdown flow and give a Control Room alarm.
6.1.9 If the gamma activity monitor becomes inoperable, liquid effluent releases may continue provided that prior to initiating a subsequent batch or continuous release, at least two technically qualified members of the facility staff independently verify the release rate calculations.
6.1.10 If the gamma activity monitor becomes inoperable during a Reactor Building Sump release, the release may continue provided that a grab sample is taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the release and analyzed for principal gamma emitters and tritium.
6.1.11 With the radioactive liquid effluent monitoring instrument inoperable, best efforts shall be exerted to return the instrument to operable status within thirty days and if unsuccessful, the failure to correct the inoperability in a timely f ashion siiall be explained in the next Annual Radioactive Effluent Release Report.
FORM (D)372 22 3M3
DPP 5.412 O. Public FORT ST. VRAIN NUCLEAR GENERAT.NG STATION Pcgn 1 64 SGTVice*
PUBUC SERVICE COMPANY OF COLORADO 1
6.1.12 If the recorder associated with the gamma activity monitor becomes inoperable, liquid effluent releases may continue provided the I
count rate of the monitor is recorded at least once per four hours during actual releases.
6.1.13 Best efforts shall be exerted to return the recorder to operable status within thirty days and if unsuccessful, the failure to correct the inoperability in a timely fashion shall be explained in the next Annual Radioactive Effluent Release Report.
6.1.14 If the blowdown flow measuring devices become inoperable, liquid effluent releases may continue provided the flow rate is estimated at least once per four hours during actual releases.
Flow rate can be estimated using the Parshall Flume in the liquid discharge pathway.
6.1.15 Liquid releases from the PCRV Shield Water System may be performed after the water in the PCRV has been processed to the extent that tha concentrations of Co-60 and Cs-137, in the entire PCRV water volume are less than approximately 1.0% of the 10CFR20 MPC limits, and after tritium has been reduced to less than the 10 CFR 20 MPC limit.
The water may be sent directly uc the discharge line where it will be diluted with blowdown flow and released.
At that tinc, the liquid waste holdup tank will not be required to be used and the entire PCRV will be considered a
{
process tank and releases will be made l
directly to the dilution point, as long as no activities are in progress inside the PCRV that could stir up additional contaminants and release them into the PCRV Shield Water System.
6.2 Licuid Effluent Surveillance Recuirements 6.2.1 The level alarms and pump interlocks on the two liquid waste receiver tanks and monitoring tank shall be tested once per year.
6.2.2 The liquid effluent discharge blocking valve shall be functionally tested prior to each release.
nnua m n me L__________________.______m
DPP 5.4.2
~Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 p
Service
- PUBLIC SERVICE COMPANY OF COLORADO 6.2.3 The gamma activity and Circulating Water blowdown flow rate monitors and their associated recorders shall be char.el-checked during each release, functionally tested prior to each release or quarterly whichever is more frequent, and calibrated once per 18 months.
NOTEi For the gamma activity monitor, the channel functional test shall also demonstrate that control Room or local alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
6.2.4 The Radioactive Liquid Waste hold up system discharge flow indicator and recorder shall be channel checked daily during releases and calibrated once per 18 months.
6.2.5 Channel check of flow instrumentation 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
6.2.6 During continuous releases, the liquid effluent discharge shall be sampled once per week and analyzed per 6.1.3 above.
6.3 Licuid Effluent Coroliance with 10CFR20 6.3.1 In order to show compliance with 10CFR20, the concentration of radionuclides in liquid effluents will be determined and compared to maximum permissible concentrations (MPC) as defined in Appendix B, Table II, of 10CFR20.
6.3.2 Concentrations of radioactivity in effluents prior to dilution will be determined by sampling and analysis.
FORM (D) 372 3643
DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 12 64 SGIVlCG*
PUBlic SERVICE COMPANY OF COLORADO 6.3.3 Concentrations of radioactivity in diluted effluent will be calculated using these results prior to and following each batch release.
6.3.4 The concentration of the various radionuclides in the liquid effluent prior to dilution will be divided by the minimum dilution flow to obtain the concentration at the unrestricted area.
This calculation is shown in the following equation:
C, R Conci =
MDF Where:
Conc, = Concentration of radionuclide, i, at the unrestricted area in Ci/mt; C, = Concentration of radionuclide, i, in the potential batch release in C1/mt; R = Release rate of the batch in gpm; MDF = Minimum Dilution Flow in gpm.
6.3.5 The projected concentration in the unrestricted area will be compared to the concentration in Appendix B, Table II, of 10CFR20 as follows:
E (Conc )
f s1 (MPC )
3 Where:
MPC, = Maximum Permissible Concentration of radionuclide, i, from 10CFR20 in Ci/mt.
FORM (D)372 22-3M3 l
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DPP 5.4.2 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 64 SerVICO*
PUBLIC SERVICE COMPANY OF COLORADO l
6.4 Licuid Effluent Doses - Compliance with 10CFR50 6.4.1 Doses resulting from liquid effluents will be calculated monthly to show compliance with 1
A cumulative summation of total body and organ doses for each calendar quarter and calendar year will be maintained.
Projected releases for the next month will also evaluated by the Facility Support staff as necessary to ensure compliance with 10CFR50.
6.4.2 Dose calculations will normally only be performed for tritium.
Dose calculations for any other radionuclides will only be performed if their undiluted concentration exceeds 1% of their respective 10CFR20 MPC.
6.4.3 Dose calculations will be performed for the most reasonably conservative pathways identified in the Environmental Report Supplement.
These include doses resulting from tritium after dilution in downstream surface or ground water as follows:
a)
Drinking water from Gilcrest town wells; b)
Ingestion of beef or poultry watered from surface water; c)
Drinking milk from cows that drink surface water; d)
Ingestion of vegetables irrigated with surface water; e)
Ingestion of fish from surface water.
6.4.4 Pathways involving consumption of tritiated water in the Goosequill Ditch will be minimized by posting of 'NO HUNTING' and 'NO FISHING' areas.
These pathways were evaluated in the Environmental Report Supplement, and will not be re-evaluated in accordance with this ODCM.
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DPP 5.4,2 IS. SUE 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 64 Service
- Pusuc suavice comeAmy or cotonano l
l 6.4.5 The dose contribution from the release of liquid effluents will be calculated monthly, as follows:
D, = EZ,A,C C,F, 3 g 3 Where:
D, = The dose commitment to the total body or any organ from the liquid effluents for the 31-day period, mrem; Cu = The average concentration of radionuclide, i, in undiluted liquid effluent for the release k, pCi/mt; Ag = The site-related ingestion dose commitment factor to the total body or any
- organ, 7,
(Attachment A);
Fu = The near field average dilution factor for ca during release, k, as determined in 6.4.6; t = The length of time for release, k, hours.
g 6.4.6 The average dilution factor (F ) for each e
release will be calculated as follows:
R*
F,=
ADDFg Where:
R = Release rate during time period, k, gpm; g
ADDF = Actual downstream dilution flow rate g
during release k, gpm, from Attachment D.
NOTE:
This is the low monthly flow downstream of the confluence of the South Platte River and St.
Vrain creek and applies to both batch and continuous releases.
l FORM tDl37 22 24
i DPP 5.4.2 IS E1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION p
g SerVICO*
PUBUC SERVICE COMPANY OF COLORADO t
1 4
6.4.7 The dose contributions from batch and f
continuous releases will be summed to determine the total dose contribution from l
liquid effluents and compare with quarterly and annual limits.
6.4.8 The monthly results will be added to the doses cumulated from the other months in the quarter of interest and in the year of interest.
6.4.9 The following relationships should hold:
i a)
Dose < 1.5 mrem /qtr total body b)
Dose < 5 mrem /qtr any organ c)
Dose < 3 mrem /yr total body d)
Dose < 10 mrem /yr any organ 6.4.10 If these quarterly or annual limits are exceeded, a special report should be submitted to the NRC stating the reason and corrective action to be taken.
If twice these limits are exceeded, a special report will be submitted showing compliance with 40CFR190.
6.5 Licuid Effluent Releases - Comoliance with Tritium Discharce Understandinc 6.5.1 Releases of liquid effluent containing tritium from PCRV Shield Water shall be controlled to ensure that the monthly average tritium concentration in downstream surface water does not exceed 20,000 pCi/1, in compliance with the Tritium Discharge Understanding between PSC and the Colorado Department of Health.
6.5.2 Tritium release rates shall be based on the following mass balance calculations:
I First, a calculated maximum tritium concentration in the Goosequill ditch shall be determined, based on available dilution flows in the surrounding surface waters.
This calculation is described in Section 6.5.3.
Then, a maximum release rate shall be determined from the calculation in Section 6.5.4.
l 1
FORM (D1372 22 3643 Y
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DPP 5.4.'2 O Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pc 3 16 64 PUBUC SERVICE COMPANY OF COLORADO 6.5.3 The Goosequill ditch represents the calculational point for determining tritium concentration to be released to the surface waters.
6.5.4 The calculated maximum tritium concentration for discharge into the Goosequill ditch shall be determined from the following mass balance equation:
i
_ OosNosp~ (Ous5csr*Oos#csv)
M -
w Om
- Where, Ma=
Calculated Maximum Tritium Concentration for discharge into the Goosequill Ditch (pCi/1);
Qm =
4.45 cfs (2000 gpm), conservatively assumed Goosequill Ditch flow rate; Q,,
=
S. Platte River monthly low flow rate, 3
Downstream, from Attachment D;
%, =
20,000 pCi/1, Tritium Concentration in S. Platte River, Downstream; Qe, =
S. Platte River monthly low flow rate, Upstream, from Attachment D (cfs);
M,=
Tritium Concentration in S. Platte e
River, Upstream (pCi/1), from weekly 6
sample data; if less than lower limit i
of detection, this will be considered zero; Q,y St. Vrain Creek monthly low flow rate,
=
Upstream, from Attachment D (cfs);
N(sy Tritium Concentration in St. Vrain
=
i Creek, Upstream (pci/1), from weekly sample data; if less than lower limit of detection, this will be considered zero.
i FORM (Da372 22 3643
DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION p
$9tVIC9' PUBLIC SERVICE COMPANY OF COLORADO I
i l
6.5.5 The maximum in-plant release rate shall be determined from the following mass balance equation:
Ouw OYCO~0 5BD 8
M, m
i
- Where, Quy Radioactive Liquid Waste release flow
=
rate (gpm);
ay Tritium concentration in Radioactive M
=
Liquid Waste (pCi/1), based on sampling prior to release; Qg 1100 gpm, conservative Goosequill
=
Ditch flow rate; M
Maximum Tritium Concentration for
=
a discharge into the Goosequill Ditch j
(pCi/1), obtained from Step 6.5.4 above; 4
Og Bypass / Blowdown flow rate (gpm);
=
Me Tritium concentration in
=
Bypass / Blowdown water (pCi/1), based on weekly sample data from storage pond; if less than the lower limit of I
detection, this will be considered Zero.
l 6.5.6 Monthly flow rates for the S.
Platte River l
(upstream), the St. Vrain Creek (upstream),
and the combined downstream flow are based on l
the Monthly Low Flow Rates in Attachment D.
I 6.5.7 Upstream tritium concentrations in the S.
Platte River, the St. Vrain Creek, and the storage ponds will be determined from weekly sampling and analysis.
l l
[
FOstM (D)372 3643
DPP 5.4.2 O SOfVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION P
8o PUIUC SERVICE CDMPANY OF COLORADO 6.5.8 During each batch release, during continuous releases, or once per day a sample from the Goosequill ditch downstream of the release point shall be collected and analyzed for tritium concentration.
6.5.9 Copies of the analysis results shall be provided to the PSC Radiation Protection Manager and the WT Project Radiation Protection Manager.
6.5.10 Actual tritium concentrations in the downstream S. Platte River shall be determined by analyzing water samples taken at the Milliken bridge.
L 6.5.11 A representative grab sample of S. Platte River water shall be taken once per day during the first 90 days of releases from the PCRV Shield Water, and at least once per week thereafter.
6.5.12 If tritium concentration in the downstream So.
Platte River Water exceeds 19,000 pCi/1, both the PSC Radiation Protection Manager and the WT Radiation Protection Manager shall be notified.
6.6 Licuid Effluent Monitor Alarm Setooint Determination:
Continuous Releases 6.6.1 The liquid activity monitor setpoints are determined based on an NIST traceable gamma source isotopic calibration of the monitors.
6.6.2 Based on the sensitivity of the monitor (gCi/mt/ cpm), a monitor response (cpm) corresponding to the unrestricted area MPC for the most restrictive gamma isotope present in the liquid waste system or the Reactor Building Sump (as found during 10CFR61 surveys and analysis of liquid waste release samples) or the PCRV Shield Water System effluent is determined using the following:
j FORM (D)772-22 3643
DPP 5.4.2
~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 19 of 64 SerVlCO*
PUBUC SERVICE COMPANY OF COLORADO 1
i 1
' * * '*A "A "' " I V 'A I"')
1-Alarm setpoint(cpm)
=
(2) Sensi tivi ty (p Ci/mt/ cpm)
I
)
Where: 2 = ALARA Factor.
(
1 i
6.6.3 The maximum allowable alarm setpoint for continuous releases is obtained by reducing the monitor response (cpm) from 6.7.2 above by a factor of 2.
This is done in the interest i
of ALARA.
6.7 Licuid Effluent Monitor Alarm Setooint Determination:
l Batch Releases 6.7.1 The alarm setpoints for RT-6212 and/or RT-6213 will be calculated prior to each batch release 3
~
from the Liquid Waste Monitoring Tank, Receivers, Reactor Building Sump, or PCRV Shield Water System as applicable.
NOTE:
If, as a result of analysis, no gamma activity is identified, monitor alarm setpoints will be the same as for continuous releases.
4 6.7.2 If gamma activity is present, the expected i
monitor response (cpm) will be determined for each identified gamma emitting isotope and monitor setpoint as follows:
1 EXPECTEDcpm = [ (Conc (pCi/mt)) lMonitorSensitivityg (cpm /pC1/mt} }
3 l
j Where:
i Conc, = the concentration of radionuclide i in i
pCi/ml and; l
Monitor Sensitivity $ = the sensitivity of the
{
d monitor for radionuclide i in Ci/ml/ cpm.
FORM (D)372 22 3643
DPP 5.4w2 O Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 20 of 64 PUBUC SERVICE COMPANY OF COLORADO a)
For the isotope identified above that has the most restrictive MPC per 10CFR20, MPC(uCi/mi) g MonicorSens1tivicy(uCi/mt/ cpm) ] = MPC(cpm)
~
b)
Determine cpm margin as follows:
MPC(cpm) (see b above) - cpm EXPECTED (see a above) = cpm MARGIN c)
Calculate alarm setpoint as follows:
55 (cpm EXPECTED + cpm MARGIN) = ALARM SETPOINT Where:
55 = 1 0 (minimum dilution (blowdown) factor) 2 (ALARAfactor) 6.8 Gaseous Effluent Generic Release Recuirements 6.8.1 The lower limits of detection (LLD) for the radioactive gaseous waste sampling and analysis program shall satisfy the following:
Tritium 1E-06 yCi/cc Particulate 1E-11 Ci/cc 6.8.2 The principal gamma emitters for which the lower limits of detection (LLD) specification applies are the following radionuclides:
Mn-54, Co-60, 2n-65, Cs-134, Cs-137, and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be considered.
Other reactor produced gamma emitters that are identified shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
FORMID1372-22 3643
DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 P
21 Service
- PUBUC SERVICE COMPANY OF COLORADO 6.8.3 At least one Reactor Building exhaust fan shall be operating whenever gaseous effluent releases are taking place.
6.8.4 Meteorological data shall be obtained and recorded hourly during gaseous effluent releases from the Reactor Building Exhaust Stack in accordance with Section C.1 of Reference 4.13.
6.8.5 During gaseous effluent releases from the Reactor Building Ventilation Exhaust Stack, one particulate sampler shall be operable.
6.8.6 If the required particulate sampler becomes inoperable, gaseous effluent releases from the Reactor Building Ventilation Exhaust Stack may continue provided an alternate sampler is placed in operation during gas releases.
6.8.7 If the gaseous waste holdup system effluent flow rate measuring device or the Reactor Building Exhaust Stack flow rate measuring device become inoperable, releases may continue provided the flow rate is estimated at least once per four hours.
6.8.8 The flow rate from the Reactor Building Exhaust Stack can be estimated by observing how many Reactor Building exhaust fans are operating.
6.8.9 Flow rate from the gaseous waste holdup system can be estimated by performing a pressure decay evaluation.
6.9 Gaseous Effluent Batch Release Recuirements 6.9.1 The allowable batch release rate, r, is calculated as follows:
C"'
3 (MPC) y, s2.18EPcm /sec r
FORM (D)372 22 3543
DPP 5.4'2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION p
Service
- PUBLIC SERVICE COMPANY OF COLORADO i
i h
Where:
Co = concentration in Ci/std.cc of j
= maximum permissible concentpation MPC 1
g of tritium, per 10CFR20, in Ci/cm,
r = release rate in std.cc/sec.
3 2.18E9 cm /sec = The inverse of the annual averagp dilution factor of 4.59E-10 sec/cm at 100 meters.
1 NOTE:
If this condition cannot be met, immediate action shall be taken to terminate release from the gas waste system.
6.9.2 Prior to a batch radioactive release, the contents shall be sampled and analyzed for tritium to determine that releases will be in compliance with 6.9.1 above.
6.10 Gaseous Effluent Surveillance Recuirements 6.10.1 During continuous gaseous effluent releases, a
grab sample shall be obtained once per week and analyzed for tritium.
i 6.10.2 The gaseous effluent particulate sample filter shall be analyzed once per week for gamma emitters described in 6.7.2 above.
6.10.3 The gaseous effluent particulate sampler shall be channel-checked daily, and flow indicator calibrated once per 18 months and following maintenance on the flow indicator.
6.10.4 The gaseous effluent tritium sampler flow indicator shall be calibrated once per 18 months and following maintenance on the flow indicator.
6.10.5 Reactor Building Ventilation Exhaust flow recorders and flow indicators shall be channel-checked daily and calibrated once per 18 months.
FORM (D)272 22-3t43
DPP 5.4.2
~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 64 Serv lCO' PUBUC SERVICE COMPANY OF COLORADO l
6.10.6 Meteorological System instrumentation shall be calibrated semi-annually to ensure meeting the system accuracies presented in Reg. Guide 1.23 (Reference 4.14).
6.11 Gaseous Effluent Dose Rate - Comoliance with 10CFR20 6.11.1 Dose rates resulting from the release of tritium and particulates with half lives greater than eight days shall be calculated to show compliance with 10CFR20.
6.11.2 The limits of 10CFR20 is conservatively applied on an instantaneous basis at the hypothetical worst case location.
i 6.11.3 The dose rate in unrestricted areas resulting from the release of tritium and particulates with half lives greater than eight days is limited to 500 mrem /yr to any organ.
6.11.4 The calculation of dose rate from tritium and particulates with half lives greater than eight days will be performed monthly for all releases.
The calculations will be based on the results of analyses obtained pursuant to 6.9.2.
6.11.5 To show compliance with 10CFR20, the equation below will be evaluated for tritium and radioactive particulates with half lives greater than eight days identified in gaseous i
effluent releases.
E iP,(X/0,0j,) + (P,,+P,+P,) (D/0,0j,) } +
3 3
3 E[ (P,+P,+P,) (X/0,0j,)] s 500 mrem 3
3 3
Where:
Pu = Infant critical organ dose parameter for radionuclide, i, other than tritium {or the inhalation pathway mrem /yr per Ci/m (ATTACHMENT B) use P for tritium; 3g i
FORMIDI772 22 3643 I
~
DPP 5.4.'2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE'1 Paga 24 of 64 Service
- PUBUC SERVICE COMPANY OF COLORADO i
Pg = Infant critical organ dose parameter for radionuclide, i, other than tritium for the ggound plane pathway mrem /yr per Ci/sec per m
(ATTACHMENT B);
j P, = Infant critical organ dose parameter for
{
ie radionuclide, i, other than tritium for thg cow milk pathway mrem /yr per Ci/sec per m' (ATTACHMENT B) use P for tritium; 3ge,
1 P
= Infant critical organ dose parameter for ira51onuclide, i, other than tritium for the i
goat milk pathway mrem /yr per Ci/sec per m 2 (ATTACHMENT B) use P, for tritium; 3
3 (x/Q)g = 4.59E-04 sec/m, Annual average j
dilution factor at 100 meters; i
Qu = The release rate of tritium from the stack for the week of interest, Ci/sec; (D/Q)
= 2.63E-07 m'3 annual average l
depos,ition factor at 100 meters.
4 l
6.11.6 Utilizing Tables E-5 and E-14 of Regulatory i
Guide 1.109, the critical age group for j
tritium for inhalation is teen, and for l
ingestion of cow and goat milk, the critical age group is infant.
6.11.7 Attachment B reflects the ICRP-30 dose conversion factor for tritium of 6.4 E-8 4
j mrem /pci.
6.11.8 Dose calculations will be made once per month.
6.11.9 The source term Qg will be determined from the results of the Gas Waste Surge tank and Reactor Building Ventilation Exhaust stack j
tritium analyses, and the analysis of weekly reactor stack particulate filters.
6.11.10 These source terms include all gaseous releases from FSV and will be recorded and reported as the total dose for compliance with 10CFR20.
J FORM tD1372.*2 M
DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 25 of 64 SerVICO' PUBUC SERVICE COMPANY OF COLORADO 1
6.12 Gaseous Effluents - ComDliance with 10CFR50 6.12.1 Doses resulting from the release of tritium and particulates with half lives greater than eight days must be calculated to show compliance with Appendix I of 10CFR50.
6.12.2 The calculations will be performed monthly for all gaseous effluents.
6.12.3 The worst case dose to an individual from tritium and particulates with half lives greater than eight days in gaseous effluents released to unrestricted areas is determined by the following expression:
3.17E-BE E R33a (W,O,)
y g i
During any calendar quarter or year the following relationships should hold:
Dose < 2.5 mrem per quarter Dose <5 mrem per calendar year Where:
3.17E-8 = The inverse of seconds in a year.
R,Ticnuclipei,pathwayj
= The dose factor for each identified ra
, aq and ci/m,e group a, organ k, m mrem /yr per W, = Dispersion parameter for estimating dose i
to an individual from stack releases.
For radionuclides other than tritium, x/Q is used for the inhalation pathway and D/Q is used for food and ground plane pathways.
For tritium, x/Q is used for all pathways.
l The annual average %/Q va ue, 4.59E-04 sec/m3 and D/Q value, 2.63E-07 m' at 100 meters, will be used for each gas waste release period.
Q,, = Release of radionuclide i for stack
- releases, ci.
i FORM (D) 772 3843
,-c
-~
~
DPP 5.4 2-O $9TVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 26 of 64 PUBUC SERVICE COMPANY OF COLORADO 6.12.4 The above equation will be applied to each combination of age group and organ.
6.12.5 Values of R,pg have been calculated using the methodology given in NUREG-0133 and are given in Attachment C.
6.12.6 The equation will be applied to a controlling location which will be one of the following:
residence, vegetable garden, meat animal, milk animal.
6.12.7 The selection of the receptor is discussed in Section 6.12.4, 6.12.5 and 6.12.6.
6.12.8 Doses calculated monthly will be summed for comparison with quarterly and annual limita.
6.12.9 The monthly results will be added to the doses cumulated from the other months in the quarter of interest and in the year of interest, and compared to the limits given in 6.12.1.
6.12.10 If these limits are exceeded, a special report should be submitted stating the reason and the corrective action to be taken.
6.12.11 If twice the limits are exceeded, a Special Report showing compliance with 40CFR190 will be submitted as described in 6.13.
6.12.12 The critical receptors for compliance with 10CFR50, Appendix I, will be identified.
6.12.13 This location will be the off site location with the highest X/Q and will be used for showing compliance with 10CFR20 and remain the same unless meteorological data is re-evaluated or the site bcundary changes.
6.12.14 The critical location for the tritium and particulate pathway will be selected once per year.
This selection will follow the annual land use census performed within five miles of FSV.
FORM fD1772-22-3643
DPP 5.4.2 0 ~ service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 27 of 64 PURUC SERVICE COMPANY OF COLORADO 6.12.15 Each of the following locations will be evaluated as potential critical receptors:
a)
Residences in each sector.
b)
Vegetable garden producing leafy green vegetables.
c)
All identified milk animal locations.
6.12*.16 The critical receptor will be selected based on this evaluation.
6.12.17 Following the annual survey, doses will be calculated for all newly-identified receptors and those receptors whose characteristics have changed significantly.
a)
The calculation should include appropriate information shown to exist at each location.
b)
The dispersion parameters given in this manual should be employed.
c)
The total releases reported for the previous calendar year should be used as the source term.
6.13 INFORMATION RELATED TO 40CFR190 AND 40CFR141 6.13.1 When the calculated doses associated with the effluent releases exceed twice the limits of any section, the licensee shall prepare and submit a Special Report to the Commission and limit subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to
<25 mrem to the total body or any organ (except the thyroid which is limited to <75 mrem) over 12 consecutive months.
This Special Report is to include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle (including all liquid and gaseous sources effluent pathways and direct radiation) are less than the standards in 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations.
If analysis indicates that releases resulting in doses l
namoim.22 mo
DPP 5.4.'2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE"l' O $9fVice*
Pcg3 28'of 64 PUBUC SERVICE COMPANY OF COLORADO that exceed the 40CFR190 Standard may have occurred, then a variance from the Commission to permit such releases will be requested or, if possible, action will be taken to reduce subsequent releases.
6.13.2 The " Uranium Fuel Cycle" is defined in 40CFR Part 190.02(b) as:
" Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
6.13.3 For the purposes of this ODCM, Fort St. Vrain shall be construed to be part of the " Uranium i
Fuel Cycle."
6.13.4 The Special Report will contain:
a)
A determination of which uranium fuel cycle facilities or operations, in addition to Fort St. Vrain contribute to the annual dose to the maximum exposed member of the public.
i NOTE:
Nuclear fuel facilities over five i
miles from FSV need not be considered in this determination.
b)
A determination of the maximum exposed member of the public, a
i FORMIDIT72 22 3643 l
-7
~'~~
DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ISSUE 1 Page 29 of 64
. SGIViCO*
PUBUC SERVICE COMPANY OF COLORADO c)
A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCM.
Where additional information on pathways and nuclides is needed, the best available information will be used and documented.
d)
A determination of the dose resulting from direct radiation from the plant and storage facilities.
6.13.5 The total body and organ doses resulting from liquid effluents from FSV will be summed with the doses resulting from gaseous releases.
6.13.6 These doses will be based upon releases from FSV during the past three quarters and from the quarter in which twice the specification was exceeded.
6.13.7 The doses from FSV will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle.
6.13.8 The direct dose components will be determined by either calculation or actual measurement.
6.14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 6.14.1 The Radiological Environmental Monitoring Program is conducted to provide data on levels of radiation and radioactive material in the site environs.
The program discriminates between those changes in environmental radiation and radioactivity levels resulting from radioactive releases from the Fort St.
Vrain Station and those changes attributed to other sources such as worldwide fallout from i
weapons testing.
The program evaluates the l
relationship between quantities of radioactive material released in liquid and gaseous effluents and resultant radiation doses to j
individuals from principal pathways of exposure.
The results of this program are used to verify the effectiveness of inplant measures applied to control the release of radioactive materials.
l l
l FORM (D)372 22 3f43
DPP 5.d.2 Public FORT ST. VRAIN NUCLEAR GENERATli4G STATION SCTVICO PCg3 3 64 PUBLIC SERVICE COMPANY OF COLORADO 6.14.2 The Radiological Environmental Monitoring Program is described in ATTACHMENT F.
6.14.3 A pre-operational environmental radiation surveillance program for the Fort St. Vrain Station environs has been conducted for Publi Service Company of Colorado by Colorado Statec University.
Continuous operation of this program since March, 1969, has provided baseline data which will be utilized as control values for statistical analysis of th results of the decommissioning radiological e
surveillance program.
6.14.4 This ODCM specifies the requirements for the Radiological Environmental Monitoring Program which will continue to be the responsibility of Public Service Company of Colorado.
6.14.5 Additional monitoring in the vicinity of the facility may be conducted or coordinated by other organizations, notably the Colorado Department of Health.
6.14.6 The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from the station operation.
6.14.7 Sampling locations were selected on the basis of local meteorological conditions and airborne concentrations calculated from those conditions, proximity of the plant to residences and communities, and other considerations in accordance with Table F-1.
Each radiological environmental monitoring report shall contain a map and tables which present detailed information regarding sampling station locations.
FORM tD1372 360
=.mm mW 9.e-M
1 DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 31 o 64
$9TVICe*
PUBUC SERVICE COMPANY OF COLORADO 6.14.8 The sampling and collection frequencies indicated in Table F-1 were selected on the basis of filter loading, crop harvest time,
{
calculated potential human doses from plant effluents, and other considerations.
6.14.9 Samples will be analyzed in accordance with Table F-1 for radionuclides which may be attributable to effluents released from the facility.
Table F-2 indicates the achievable detection capabilities for environmental sample analysis based upon the instrumentation and analytical procedures analyzed.
6.14.10 The requirement for participation in the Environmental Protection Agency crosscheck program or similar program is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
6.14.11 The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10CFR50 to
" Identify changes in the use of unrestricted areas (e.g.,
for programs for evaluating doses i
to individuals from principal pathways of exposure."
6.14.12 The 50 square meter garden cettsidering 20%
i i
used for growing broad leaf vegetation (i.e.,
similar to lettuce and cabbage) and a vegetation yield of 2 kilograms per square meter will produce the 26 kilograns per year assumed in Regulatory Guide 1.109 for child consumption of leafy vegetation.
~
7.0 REPORTING REOUIREMENTS 7.1 An Annual Radiological Environmental Monitoring Report shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and analyses or trends of the results of the REMP for the reporting period.
The material provided shall be consistent with Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10CFR50.
FORM (DI 772 3643
DPP 5.4.,2,
Public FbRT ST. VRAIN NUCLEAR GENERATING STATION O$9fVICO' Paga 32 o 64 PUBUC SERVICE COMPANY OF COLORADO 7.2 An Annual Radioactive Effluent Release Report covering activities during the previous 12 months shall be submitted within 90 days after January 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid warete released from the unit during the reporting period.
The report shall also include a copy of the ODCM if any changes were made during the reporting period as required by Decommissioning Technical Specification 5.10.
The material provided shall be in t
conformance with 10CFR50.36a and Section IV.B.1 of Appendix I to 10CFR50.
7.3 Within 30 days after each calendar month after releases of PCRV Shield Water have been initiated and until all PCRV Shield Water has been released, a report shall be submitted to the Colorado Department of Health Water Quality Control Division summarizing the release calculations and sampling results for tritium releases made during the month.
i i
1 1
FORM (D1272 3.M
DPP 5.4.2 O ~SGIVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION At h
A PUBUC SERVICE COMPANY OF COLORADO Page 33 of 64 Ag Values (Dose Factors) for Fort St. Vrain A
is calculated for an adult using the following equation:
g Ag 1.34 E6 (IF,) (DFg)
=
Where:
1.34 E6 =
Unit conversion factor, (1 E6 pCi/gCi) (1 E3 ml/1) (1 month /744 hr)
IF, Intake factor, based on consumption rates in
=
Since tritium does not affect any one organ more than the rest, IF, for tritium is determined by converting the various pathways identified in 6.4.3 to an equivalent intake of tritiated water (HTO) for the month of the calculation, as follows:
Beef / Poultry (110 kg/yr) (1/12 yr) (0.6 L HTO/kg)
=
5.5 t/ month
=
Milk (400 t/yr) (1/12 yr)
=
33.3 t/ month
=
Vegetables (340 kg/yr) (1/12 yr) (0.75 L HTO/kg)
=
21.2 t/ month
=
Fish (21 kg/yr) (1/12 yr) (0.9 L HTO/kg)
=
1.6 t/ month
=
Drinking water: Assume Gilcrest well water with a tritium concentration 1/20 of that in surface water, times a conservative factor of 2, or 0.1.
(2 t/ day) (31 days / month) (0.1)
=
6.2 t/ month
=
Total IF, 67.8 L HTO/ month
=
DFg Dose conversion factor, from ICRP-30.
For
=
tritium, DF = 6.4 E-8 mrem /pci For tritium, Ag (1.34 E6 pCi-mt-mo/4Ci-t-hr) ) (67. 8 t /mo) (6. 4 E-
=
08 mrem /pCi) 5.81 mrem /hr per 4Ci/mt
=
FORMt01372 22 3M3
I DPP 5.4,.2, [
1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION
.AttEch. A ISSUE 1 Service
The other radionuclides of interest during decommissioning are Co-60 and Cs-137.
l The A factors for these radionuclides are based on the same g
intake factor, IF,, determined for tritium, 67.8 t/ month.
ICRP-30 dose conversion factors are used.
A dose factors for Co-60 and Cs-137 are as follows:
g Co-60 Cs-137 Gonads 2.42 E03 4.70 E03 Breast 1.71 E03 4.03 E03 R. Marrow 1.85 E03 4.37 E03 Lungs 1.68 E03 4.37 E03
~
SI Wall 2.76 E03 4.70 E03 ULI Wall 3.23 E03 4.70 E03 LLI Wall 4.70 E03 4.70 E03 Liver 4.37 E03 Thyroid 4.37 E03 Bone Surf.
4.37 E03 Remainder 2.92 E03 5.04 E03 rcmuam 22 me l
l
$r 5
P VALUES FOR FORT ST. VRAIN i
3 (n "U is Teen Ground Infant Infant SC g
Isotope Inhalation Plane Cow Milk Goat Milk 2.7, OO 11 - 3 7.72E2 0
1.45E3 2.96E3 g
e
.c o=
3 Units are mrem /yr per pCi/m for the inhalation pathway, and mrem /yr per pCi/sec per m for Q
the food and ground plane pathways.
,9 m <
3 m
== b MZ n5 O O E
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R VALUES FOR FORT ST. VRAIN*
j PATl!WAY = GOAT MILK m,
AGE GROUP = ADULT g
GC
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[
NUCLIDE TOTAL GI-BONE LIVER KIDNEY TliYROID LUNG SKIN BODY TRACT OO S
H3 9.57E 02 9.57E 02 0.00E 00 9.57E 02 9.57E 02 9.57E O2 9.57E 02 9.57E02 PATliWAY = GOAT MILK o m AGE GROUP = TEEN
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NUCLIDE TOTAL GI-BONE LIVER KIDNEY TilYROID LUNG SKIN nm BODY TRACT
.H m
H3
- 1. 24 E 03 1.24E 03 0.00E 00 1.24E 03
- 1. 24 E 03 1.24 E 03 1.24E 03 1.24E0 g
82 PATIIWAY = GOAT MILK m
b AGE GROUP = CliILD 0o
!{o NUCLIDE TOTAL GI-BONE LIVER KIDNEY THYROID LUNG SKIN BODY TRACT m
E H3 1.97E 03 1.97E 03 0.00E 00 1.97E 03 1.97E G3 1.97E 03 1.97E 03 1.97E03 O znf PATIIWAY = GOAT MILK AGE GROUP = INFANT O H r-
=;
NUCLIDE TOTAL GI-BONE LIVER KIDNEY Tl!YROID LUNG SKIN Ob BODY TRACT gy l
[
H3 2.99E 03 2.99E 03 0.00E 00 2.99E 03 2.99E 03 2.99E 03 2.99E 03 2.99E03 i
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- R Values in units of mrem /yr per Ci/m for inhalation and tritium.
,g
- MC*
O in D m j
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R VALUES FOR FORT ST. VRAIN*
g PATIIWAY = INilALATION mm AGE GROUP = ADULT 9
@C
$. =U-g NUCLIDE TOTAL GI-BONE LIVER KIDNEY Tl!YROID LUNG SKIN BODY TRACT OO 11 3 7.68E 02 7.68E 02 0.00E 00 7.68E G2 7.68E 02 7.68E 02 7.68E 02 7.68E02 PATIIWAY = INHALATION m m AGE GROUP = TEEN EO d
C NUCLIDE TOTAL GI-BONE LIVER KIDNEY TIIYROID LUNG SKIN O (n BODY TRACT m
M 11 3 7.74E 02 7.74E 02 0.00E 00 7.74E 02 7.74E 02 7.74E O2 7.74E O2
_7.74E02__
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kh NUCLIDE TOTAL GI-BONE LIVER KIDNEY TIIYROID LUNG SKIN BODY TRACT gn H3 6.83E 02 6.83E 02 0.00E 00 6.83E 03 6.83E 02 6.83E 02 6.83E 02 6.83E02 0M PATIIWAY = INilALATION ny AGE GROUP = INFANT O d O Z NUCLIDE TOTAL GI-BONE LIVER KIDNEY THYROID LUNG SKIN a
O BODY TRACT
> m O
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H3 3.94E O2 3.94E 02 0.00E 00 3.94E 02 3.94E O2 3.94E 02 3.94E 02 3.94E02 doz N
1!
- R Values in units of mrem /yr per Ci/m for inhalation and tritium.
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION
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PUBLIC SERVICE COMPANY OF COLORADO Page 41 of 64 MONTHLY SOUTH PLATTE RIVER LOW FLOW RATES (in cubic feet per second)
Upstream Upstream Downstream Month S.
Platte St. Vrain Total Qrm Qow
- Qns, January 308 97 405 February 147 102 249 March 56 84 140 April 46 72 118 May 46 72 118 June 77 68 145 July 44 174 218 August 58 118 176 l
September 5
114 119 l
October 5
114 119 November 21 109 130 December 250 97 347 Actual Downstream Dilution Flow Rates Month Flow Rate (com)
January 182,000 February 112,000 March 63,000 April 53,000 i
May 53,000 l
June 65,000 l
July 98,000 August 79,000 September 53,000 October 53,000 November 58,000 December 156,000 l
l nmem n-sea
DPP 5.4r2,,
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. E ISSUE 1 SerVICO*
PUBLIC SERVICE COMPANY OF COLORADO page 42 of 64 ODCM BACKGROUND INFORMATION Radioactive Licuid and Gaseous Waste System Backaround 1.
The radioactive liquid and gaseous waste treatment systems are designed to ensure compliance with 10 CFR 20 and 10 CFR 50, Appendix I.
2.
The Radioactive Liquid Waste System, System 62, is designed to collect, treat, and permit sampling, analysis and monitoring of all potentially radioactive liquid wastes discharged from the reactor plant, and is described in Section 2.3.3.10 of the Decommissioning Plan.
Radioactive liquid waste is collected, monitored, and processed, if necessary, by the radioactive liquid waste system before being discharged from the plant.
Effluent from the radioactive liquid waste system is diluted in the cooling tower blowdown / bypass line.
The activity in the cooling tower blowdown / bypass line is maintained below the maximum permissible concentration (MPC) specified in 10 CFR 20.
3.
The Radioactive Gas Waste System, System 63, is designed to collect, treat, and permit sampling, analysis, and monitoring of potentially radioactive gases discharged from the plant, and is described in Section 2.3.3.11 of the Decommissioning Plan.
All radioactive gases are directed to the reactor building ventilation system, filtered, and discharged at high velocity at the top of the reactor building, about 180 ft.
above grade.
Average offsite radioactivity concentrations are significantly less than the MPCs specified in 10 CFR 20.
4.
Solid radioactive wastes may be processed onsite or sent offsite for volume reduction or other processing.
These processing activities, as well as activities associated with the packaging, storing, and shipping of radioactive wastes, are described in Section 3.3 of the Decommissioning Plan.
FORM (D)T?2-22 3M3
s DPP 5.4.2 pub l[C FORT ST. VRAIN NUCLEAR GENERATING STATION a
SOIViCO' PUBLIC SERVICE COMPANY OF COLORADO Page 43 of 64 Ecuirment Descrintions 1.
Liquid Effluent Activity and Flow Rate Monitors, RT-6212, RT-
Upon detection of high concentrations of gross gamma activity, these activity monitors will automatically alarm, shutdown the Liquid Waste l
Transfer Pumps, shutdown the Reactor Building sump pumps, and shut the block valves in the liquid waste discharge line.
A flow switch, FS-4101-1, is provided in the cooling tower bypass / blowdown line to automatically alarm, shutdown the Liquid Waste Transfer Pumps, shutdown the Reactor Building sump pumps, and shut the block valves in the liquid waste discharge line in the event of low cooling tower bypass /
blowdown flow conditions that would not provide sufficient.
dilution of radioactive liquid effluent.
4 2.
Air Flow Measurement Ventilation system flow is measured at the outlet of the system.
Above-normal flow rates are alarmed to ensure that allowable activity release rates are not exceeded.
3.
Meteorological Instrumentation Two meteorological towers, one 60 meters high and the other 4
10 meters high, are installed approximately one-half mile north of the plant.
This instrumentation is provided for determination of dispersion coefficients and to provide data for the annual effluent release report.
The 60 meter tower is the primary tower and the 10 meter tower is a backup.
The 60 meter tower provides information on wind speed and wind direction at 58 meters and 10 meters elevation, temperature at the lower level, temperature difference between the upper and lower levels, dewpoint, and precipitation.
The 10 meter tower provides information on wind speed, wind direction, temperature and dewpoint.
Both towers supply data to a data logger.
Additionally, the 60 meter tower supplies data to chart recorders located in the control room.
Both towers 3
also supply data to chart recorders located in a weather station, which is also approximately one-half mile north of the plant.
There is a gas-driven electric generator for emergency electrical supply in the event of loss of power to l
the towers and weather station.
FORM (DI372-22 3643
DPP 5. 4. 2. -
O ServiC9' FOHi ST. VRAIN NUCLEAR GENERATING STATION At
- h. F Public j
PUBUC SERVICE COMPANY OF COLORADO Page 44 of 64 i
J j
1.0 Radiolocical Environmental Monitorina Procram 4
1.1 A Radiological Environmental Monitoring Program shall be conducted in accordance with Table F-1.
1.2 The radiological environmental monitoring samples shal be collected from the specific locations given in tabl l F-1, and shall be analyzed pursuant to the requiremente of Table F-1 and the detection capabilities required bs Table F-2.
y 1.3 If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any quarter sampling period exceeds the reporting level 3
given in Table F-3, a special report shall be submitted i
to the Nuclear Regulatory Commission within 30 days.
1 A
1.4 Analytical techniques used shall be such that the detection capabilities in Table F-2 are achieved.
1.5 Radiological sampling station locations shall be delineated in maps and in written descriptions contained in each Annual Radiological Environmental Monitoring Report.
All changes in sampling station locations which occur through the year shall be i
explained in each annual report.
1.6 i
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous j
conditions, seasonal unavailability, malfunction of automatic sampling equipment, reasons.
and other legitimate equipment malfunction, every effort shall be made toIf i
a complete corrective action prior to the end of the next I
sampling period.
schedule shall be documented in the annual report.All dev i
1.7 If milk or "resh leafy vegetable samples are unavailable from one or more of the sample locations 4
required by Table F-1, locations for obtaining replacement samples shall be identified and added to i
within 30 days.the Radiological Environmental Monitoring Program samples were unavaiThe specific locations from which monitoring program.lable may then be deleted from the s
the cause of the unavailability of samples andIn lieu o (LER),
the new location (s) shall be identified in the next Annual Radiologicalfor obtain Environmental Monitoring Report.
The report shall also FORM (D)372 22 3643
~.. _. -
DPP 5.4.2 O~Public FORT ST. VRAIN NUCLEAR GENERATING STATION At h
F SGIVice*
PUBLIC SERVICE COMPANY OF COLORADO Page 45 of 64 include a revised figure (s) and table for the ODCM reflecting the new location (s).
1.8 Analyses shall be performed on radioactive materials supplied as part of a documented inter-laboratory comparison program.
1.8.1 Analysis shall be performed on radioactive samples supplied by the EPA crosscheck program.
This program involves the analysis of samples provided by a control laboratory as well as with other laboratories that receive portions of the same samples.
Media used in this program (air, milk, water, etc.) may be limited to those found in the radiation monitoring program.
1.8.2 A summary of the results of analysis performed as part of the cross-check program shall be included in the Annual Radiological Environmental Monitoring Report.
1.8.3 The EPA uses the term, Estimated Laboratory l
Precision (ELP), calculated as 3a/N, as the l
control parameter where N= the number of analyses.
Whenever mean values fall outside i
this limit, the sample calculations are rechecked and the sample reanalyzed if possible.
l NOTE:
If analysis are not being performed as required, corrective actions taken to prevent recurrence shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Monitoring Report.
1.9 A census shall be conducted annually during the growing season to determine the location of the nearest resident, the nearest milk animal, and the nearest garden greater than 50 square meters (500 square feet) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 kilometers (5 miles).
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O SGIVICe*
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'AttOch. F ISSUE 1 PUBLIC SERVICE COMPANY OF COLORADO Page 46 of 64 1.9.1 When the land use census identifies a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in the ODCM, in lieu of a Licensee Event Report, the new location (s) will be identified in the next Annual Radioactive Effluent Release Report.
1.9.2 If it is learned from this census that the milk animals or gardens are present at a location which yields a calculated dose or-i dose commitment 20% greater than those previously calculated, or if the census results in changes in the sampling location, a written report shall be submitted in the next Annual Radiological Environmental Monitoring Report identifying the new location (distance and direction).
Milk animals or garden locations resulting in 20% higher calculated doses shall be added to the monitoring program within 30 days or as soon as practicable.
1.9.3 The sampling location (excluding the control sample location) having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted.
Any location from which milk can no longer be obtained may be dropped from the monitoring program after notifying the Nuclear Regulatory Commission in writing that milk samples are no longer obtainable at that location.
The results of the land use census shall be reported in the Annual Radiological Environmental Monitoring Report.
FORM (D) 372 3M3
t 5
TABLE F-1 j
DECOMMISSIONING RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (n c g
ec s
< -(7 5
Exposure Pathway Number of Samples Sampling Type and Frequency
(( ((
and/or Sample and Locations Collection Frequency of Analysis g
e AIRBORNE Tritium Oxide Samples from seven Continuous sampler Liquid j8 and Particulates locations.
operation with scintillation a m sample collection counting for Q[
Four samples from weekly or as tritium on water
,s offsite locations (in required by dust vapor extracted m
different sectors) of loading, whichever from silica gel on
$eg the highest calculated is more frequent.
each sample 5g annual average ground collected.
m z
level D/Q and airborne Qc I
X/Q.
Particulate 3O j9 Sampler:
Gross One sample from the beta radioactivity z"
vicinity of a community following filter 4 @
having the highest change, composite O z calculated annual (by location) for n"
m average ground level gamma isoto o&
quarterly. pic o2 i
D/Q.
mQ Two samples from control location 15 to 30 0
kilometers (10 to 20 5
y miles) distant and in Z
the least prevalent wind m
direction.
j m
l
.If gross beta activity in air or water is greater than ten times the yearly mean of control gg
>e sample for any medium, gamma isotopic analysis should be performed on the individual samples.
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TABLE F-1 fContinuedl t
DECOMMISSIONING RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM H
l k
(n tp
@C 5
Exposure Pathway Number of Samples
, g-and/or Sample and Locations Sampling Type and Frequency K 3*
Collection Frequency of Analysis DIRECT RADIATION Forty stations with two g
or more dosimeters or Quarterly Gamma Exposure Rate 8
one instrument for measuring and recording co dose rate continuously E$
to be placed as follows:
nm
- 1) an inner ring of m
stations in the general 9g area of the site 5>
boundary and an outer QE ring in the 4 to 5 mile 2
n range from the site with oE a station in each sector EF x 2 rings =g (16 sectors
$h of each rin 32 2
stations); eight shall be placed in special OM interest areas such as ns population centers, O d nearby residences, g$
schools, and in two or
> m three areas to serve as D y control stations.
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2 2
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Es TABLE F-1 (Continued) y DECOMMISSIONING RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM cn 13-
,e c u
s
<g 5
Exposure Pathway Number of Samples Sampling Type and Frequency gg and/or Sample and Locations Collection Frequency of Analysis g
9 WATERBORNE m m surface One sample upstream, Upstream samples Gamma isotopic co each stream, one sample collected monthly, analysis and E
-4 downstream Downstream sample tritium weekly om aliquot taken ca -*
continuously 5g S?
Surface One sample in immediate Composite continuous QZ (Farm Pond) area of discharge sample over one week Gamma isotopic 2
n
((E period.
Composite analysis and O
collected weekly tritium weekly
>m 2< 0 0 2 9
o>
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TABLE F-1 (Continued) j DECOMPISSIONING RADIOLOGICAL ENVIBQHMENTAL MQNITOBING ?BQGR8H to T E
SC Exposure Pathway Number of Samples Sampling Type and Frequency QE 5
and/or Sample and Locations Collection Frequency of Analysis gg 9
Ground Samples from two sources Weekly from Facility Gamma isotopic and e
most likely to be Area, Quarterly for tritium affected Reference Area Drinking One sample from the Weekly composite for i
cO a
nearest water supply tritium, gross m
which could be affected beta, and gamma
.H by facility's discharge isotopic analyses m
weekly
$<y One sample from a 5g control location "nE Sediment from one sample from Semi-annually hP Shoreline downstream area with 1
9 existing or potential Gamma isotopic recreational value analyses semi-4 @
annually 0 $
One sample in effluent Monthly n"
pathway oM oE Gamma isotopic gU analyses monthly ay O >d O
i 2
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rt 4 O H tt 4 U3 &
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2 TADLE F-1 fContinued) j DECOMPISSIONING RADIQLQGICAL ENVIRONMENTAL MONITQBING PROGRAM mg SC Y
Exposure Pathway Number of Samples Sampling Type and Frequency QQ and/or Sample and Locations Collection Frequency of Analysis gg INGESTION G
e Milk Samples from milking Semi-monthly when Gamma isotopic animals in all locations animals are on analysis semi-co up to a total of three pasture, monthly at monthly when a y locations, within 5 other times animals are on nm kilometers pasture, monthly at u
-H other times E
One sample from milking
$ >g animals in each of three QE areas between 5 to 8 z
kilometers distant oE having the highest dose Er potential jh 2
One sample from milking
<0 m animals at a control Semi-monthly when OM location (15 to 30 animals are on Gamma isotopic n$
kilometers distant and pasture, monthly at analysis semi-O d In the least prevalent other times monthly when g$
, wind direction) animals are on
>w pasture, monthly at gy j
other times d
'The dose shall be calculated for the maximum organ and age group using the methodology O.
contained in Regulatory Guide 1.109 and the actual parameters particular to the site.
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i TABLE F-1 (Continued) j i
QECOMMISSlQHING rap _IQLOGIQ L ENVIRONEENTAL MOFlTORING PROGRAM mg E
OC Exposure Pathway Number of Samples Sampling Type and Frequency QQ and/or Sample and Locations Collection Frequency of Analysis yg S
Aquatic Biota Sample fish in vicinity Semi-annually Gamma isotopic e
of discharge point, analyses and upstream and downstream tritium C O Food Products One sample of each At time of harvest E$
principal class of food Gamma isotopic nm products from any area analyses m M which is irrigated by Eg water in which liquid 5>
plant wastes have been Qz discharged.
2 n
O Tissue samples (muscle Semi-annually
{O and liver) from one head 2
of beef cattle that Tritium and gamma
$a graze near effluent isotopic analyses og ditch pathway n g O
h >Z O
0 2> en U
-4 O >do2 h
e
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TABLE F-2 (n ts' Y
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAgPLE ANALYSIS SC LOWER LIMIT OF DETECTION (LLD) #'
2 _U_
N d6 m
Analysis Water Airborne Fish Milk Food Sediment e
(pCi/t)
Particulate (pCi/kg, wet)
(pCi/t)
Products (pCi/kg, dry) or Gag (pCi/kg, wet)
,n (fCi/m )
g @H C
Gross Beta 4
5 ny 11 - 3 2000 M
m fg Cs-134 15 9
130 15 60 150 m
Cs-137 18 8
150 18 80 180 2
n Mn-54 15 130 h
9 5
Co-60 15 130 gm Zn-65 30 260 O
Mm*
0!
NOTE:
This 1.ist does not mean that only these nuclides are to be detected and reported.
Ob Other peaks which are measurable and identifiable, together with the above
> m nuclides, shall also be identified and reported.
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DPP 5.4.2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
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PUBUC SERVICE COMPANY OF COLORADO Page 54 of 64 g
I
- The LLD is defined for purposes of these specifications as the i
smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
1.10 For a particular measurement system which may include t
1 radiochemical separation:
1 g
2. 71 +4. 6 6 /5 1
T E-V*2. 22E6 Y exp (- A A C) 4 l
Where:
LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, i
VB is the standard deviation of the total 3
j background counts or of the total counts of a j
blank sample, as appropriate, as counts, T is the count time of background in minutes, I
E is the counting efficiency as counts per i
disintegration or counts per gamma for gamma spectroscopy, V is the sample size in units of mass or
- volume, 2.22E6 is the number of disintegrations per minute per microcurie, (dpm/ Ci),
Y is the fractional radiochemical yield when applicable and/or the gammas per disintegration when applied to gamma q
spectroscopy, A is, if radioactive decay correction is applicable, the radioactive decay constant for the particular radionuclide,
~
At is the elapsed time between the sample collection and time of counting.
1.11 Values of E, V, Y, and At, which are appropriate to the sample, should be used in the calculation.
FORMIDIT72 22 3843
DPP 5.4.2
^
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PUBLIC SERVICE COMPANY OF COLORADO Page 55 of 64 t
1.12 It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions.
Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Monitoring Report.
' Lower limit of detection for drinking water samples.
If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
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FORM (D)372-22 3i43
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TABLE F-4 us 93 g
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SC SAMPLING SITE DESCRIPTIONS Q E[
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area) gj' ((
G Exposure Site Location Description (see map)
Sector
- Distance, e
Pathway No.
Km Direct Pole by gate to Gooseguill road on dirt 1
1.3 eo Radiation F-1 extension of CR 21.
[$
n$y F-2 21st pole N of ditch on dirt extension of 2
1.1 h
CR21 just before road drops down to river bottom.
jg F-3 17th pole N of ditch on dirt extension of CR 3
0.7 m
2 21 or first pole N of East-West road, 2
o c
O o F-4 15th pole N of ditch on dirt extension of CR 4
0.7 EF 21, S of pump road, midway between F-3 and F-
$h 5.
2
@n F-5 lith pole N of ditch on dirt extension of CR 5
0.6 0 Z 21, near drive to pump house.
g h
F-6 8th pole N of ditch on dirt extension of CR 6
0.8 21, by a o East-West concrete Ditch, S of bridge
>m O H U
F-7 Old dairy barn, 1st pole N after crossing 7
1.2 ditch on dirt extension of CR 21.
Q F-8 1st pole W of pump house on N side of road, 8
1.3 m
O.4 km E of CR 19-1/2.
$e F-9 Pole E of first shed at intersection of CR 9
1.5 m
19-1/2 and CR 34.
4Hn4 mu F-10 Pole on NW corner of intersection of dirt 10 1.5 S $ h.*
extension of CR 19 and 34.
M*
msymu i
h TABLE F-4 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM en U 6
SAMPLING SITE DESCRIPTIONS SC (F: Fu-
'My Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area) 2 E_.
m---
Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km Direct F-11 7th pole N of intersection of dirt extension 11 1.2 Radiation of CR 19 with CR 34.
co a 2^
F-12 0.5 km S of FSV Visitor Center, take dirt 12 1.0 C
O $
road W across field, go into farmyard of Aristocrat Angus.
(If chain across road,
$h enter from CR 36).
TLD is located on pole at
$g SE corner of corral across from Aristocrat 5g Angus office.
m O C F-13 Take first dirt road S of Visitor Center.
Go 13 0.5 0!o W across railroad tracks, follow dirt road to h
metal staircase going down off dike.
TLD is taped to railing.
$ma m
F-14 2nd polo 0.1 km S intersection CR 36-1/2 and 14 1.5 05 Rd 19.
o$
n
-t F-15 2nd polo 0.7 km S of intersection of CR 38 on 15 1.5 oE CR 19.
2 0
> tn 8 [$
F-16 Pole at NE corner of potato cellar at 3 Bar 1
1.2 Ranch (Russell's).
F-17 Visitor Center, on N end of cross beam over 13 0.2 entrance.
y da F-18 Pole closest to house on SW corner, 17250 CR 16 0.8 m
19-1/2.
The address of 17250 is taped to the NO in Mountain Bell underground cable warning post.
"yg4 o tn n m A-1 Pole on NW corner of intersection of CR 44 1
6.7 M Q f *,
and CR 21.
m a e *n u
.c 3
.c
- - +
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m
i 9
h IADLE F-4 y
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM o,9a 6
SAMPLING SITE DESCRIPTIONS eC (F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area) 2_ E_[
g O
Exposure Site Location Description (see map)
Sector
- Distance, Pathway No.
Km e
Direct A-2 Pole on NE corner of intersection of CR 42 2
6.8 Radiation and CR 25-1/2
@o a 2 A-3 Pole on NE corner of intersection of CR 42 3
7.5 C
H and CO 60.
O A-4 1st pole NE of intersection of CR 29 and 4
7.4 Ej CR38, take CR 29 E out of Gilcrest to CR 38.
S>
0 z A-5 SE corner of CR 34 and CR 29.
Taped to road 5
7.2 "z
sign on SW corner of intersection.
o@
EF A-6 Pole on S side of CR 32 near drive to dairy 6
7.1 1
9 13278 CR 32.
$m
<o A-7 Niles Miller dairy.
0.4 km E of US 85 on 7
7.3 og 12854 CR 30.
TLD is located on pole at NE g
m corner of house.
O >
?d A-8 On CO 66 (CR 30) farm on S side of road 8
4.7 o[2 (address 9476) Pole in front of house.
J b
A-9 Corner of CO 66 (CR 30) and CR 19, Miller 9
4.6 produce stand.
Second pole S on CR 19, on E 6
side of road.
Z A-10 Pole on SE corner at intersection CR 26-1/2 10 7.8 E
and CR 15.
4 A-11 At intersection of CO 66 and CR 13, 2nd pole 11 7.2 m
n*
>c N of intersection on E side of CR 13.
omom M.
TemL
kn 6
IABLE F-4 5
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Cn =c s
SAMPLING SITE DESCRIPTIONS SC g
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area)
}[h[
no Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km e
Direct A-12 On CR 34, pole E of house N of Lake Thomas 2 12 7.2 Radiation km from I-25.
Eo a 2 A-13 Pole opposite lake, N of silage pits E side 13 5.8
{e of CR 13 2.9 km H of CR 34.
A-14 Intersection of CR 13 and CR 40, NW corner.
14 6.9 m $
A-15 Intersection of CR 42 and CR 15, NW corner.
15 6.7 QEz A-16 Intersection of CR 44 and CR 19, SW corner.
16 6.8 Qc kh A-17 Platteville school (S edge of town on Main 6
5.9 Street) pole on NW corner just outside school gm intramural field.
<om A-20 1st pole N of white picket fence and driveway 9
2.5 OM into turkey farm on S end of building that is n$
parallel with CR 19.
O d O Z R-1 Milliken School, on CR 21-1/2.
TLD is 9.3 2
U located on pole located at SE corner of Lola Park, across the street from school.
O g R-2 Johnstown school (Letford Elementary), turn 10.8 0
left at school crossing on Idaho St. onto Jay Ave. and proceed to school.
TLD is located 8
on pole at SE corner of main entrance to j
school on W side of town.
gg R-3 CSU dairy farm on W Drake, N of Vet Hospital, 45.1 UE" Fort Collins, CO.
Pole is E of hay barn next R E S."
to railroad tracks.
,M-7,
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.e e
I n.
+
v c
c-
~
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6 9
5 r
5 T8DLE F-4 5
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM us 95 h
SAMPLING SITE DESCRIPTIONS OC g
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area) 3,((
oo Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km Direct R-4 Air sampler corner US 287 and CO 66, Longmont 20.5 Radiation Dairy Store.
TLD is located on pole directly eo behind air sampler.
y$
R-7 Behind Gilcrest School quonset auditorium, 9.3 pole on SW end of school property, just m
$ <g before garage.
Waterborne F-1 Sediment from confluence of Goosdquill Ditch 1
1.3 ME Sediment and Jay Thomas Ditch.
y p$
o from Shoreline
>g i
m R-10 Sediment from S.
Platte River at bridge on CO 10.1
$g 60.
g Airborne F-7 Farm at intersection of CR 21 and CR 34.
Air 7
1.5 "5
sampler is located on west side of shop.
o&
Silica gel inside building on N end of 5E0 workbench.
N>m F-9 First shed along drive at end of Rd 19-1/2 9
1.5 oN intersection with Rd 34.
Silica gel is d
located in shed.
O F-16 Potato cellar at 3 Bar Ranch (Russell's).
16 1.2 m
Silica gel in mailbox on tree to S of pump.
$m A-19 Hunting cabin between Goosequill ditch and 1
1.7 m
Platte River.
Air sampler is on W side of HHn4 cabin, silica gel is in box on tree north of o$$m air sampler.
"@F*,
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m
- w--
w-
+-
r
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i 1
Na 6
TABLE F-4 1
3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM up N s
SAMPLING SITE DESCRIPTIONS SC g
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area)
{no Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km e
Airborne R-3 Colorado State University Dairy, W Drake Rd.,
45.1 Fort Collins, CO. W side of shed directly N 3o of main dairy building.
Silica gel inside e$
mailbox.
nm
-t
$h R-4 Intersection of US 66 and US 287, E side of 20.5 dairy store, north edge of Longmont.
Silica j$
m gel is in mailbox attached to utility pole.
j5 m
.R-11 Air sampler is located in alley behind PSC 10.5 n$
office, next to garage.
Silica gel is O n located next to air sampler in mailbox and on
!y top of pose, 13-1/2 Parish St.,
Johnstown,
$m CO.
Waterborne F-19 S Platte at dam located on dirt road E of 4
1.2 Surface pump house #3 directly E of reactor.
ny o
-4 F-20 St. Vrain creek on Rd 19-1/2, 0.3 km from 16 1.5 5E l
discharge into St. Vrain Creek.
Directly N gQ j
of reactor.
A-21 St. Vrain creek at bridge on Rd 34, E of Rd 11 2.4 d
l 19.
O
{
Waterborne A-25 Goosequill Pond outlet.
Continuous sampler 1
2.2 g
Surface located in green box adjacent to the green e
shed on N end of pond.
go m
rt w R-10 S.
Platte river at bridge on CO 60 where 10.1 "My*
j highway has just turned and headed south.
ggg7 N*t H M $3 i
~.
t e
e
$a 6
TABLE F-4 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (n u 6
SAMPLING SITE DESCRIPTIONS SC g
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area)
[
OO Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km e
i Ground F-16 Well behind residence at 3 Dar Ranch 1
1.2 (Russell's), 17578 WCR 19-1/2.
co a2 R-5 Well at 108 S.
Grace, Milliken.
9.5 hm Drinking R-3 CSU dairy W Drake Rd, Fort Collins, CO, N of 45.1 g *$
Vet Hospital.
Water sample is taken from a
hydrant inside entrance to milking parlor.
lg R-6 Gilcrest U.S.
Post Office located on Birch 9.3 2
St. and Rd 40 off IIwy 85.
Water taken from oE utility sink inside Post Office.
Er 9
Ingestion A-6 Hendrickson Dairy, 13278 Rd 32 (Grand 6
7.1
!2 Milk Avenue), 1.6 km E of US 85.
4 Q
O z A-18 Boos Dalry, 11258 W Rd 40, W of US 85 behind 2
4.7 5
g modular home.
Qg r-A-22 Percy Odenbaugh Dairy, S on dirt rd from 5
3.2 0 $
"LeRoy & Paul Odenbaugh Dairy" sign.
Dairy
$m sign on WCR 36, E of Ed 23.
Dairy sign is O g located next to mailbox of Mike Thomas.
3O A-23 Leroy Odenbaugh Dairy, 11733 Rd 36, W of Rd 4
4.1 Z
25.
.c A-24 Marostica Dairy, 20718 Rd 17, 4 miles S of CO 16 6.9 6o-
- 2 A-26 L & F Dairy (Fiechtner), E of Rd 13 on Rd 32.
11 7.8 5E 6165 WCP. 32.
S " :n y
.Ry t n., ~
5 E
6 IAEE F-4 5
RADIOLOGICAL ENVIRQEMENTAL MONITORING PROGRAM (n t3 s
SAMPLING SITE DESCRIPTIONS SC g
(F: Facility Area 0-1.6 km.
A: Adjacent Area 1.6-8 km.
R: Reference Area)
[h ao Exposure Site Location Description (see map)
Sector
- Distance, g
Pathway No.
Km Ingestion R-8 Gorzman Dairy, 2056 S CR 17, located off exit 22.5 Milk 255 W of I-25 directly N of Johnson's Corner
, o, e@
restaurant.
[0
$ ~y Fish F-19 S.
Platte at dam located on dirt road E of 4
1.1 pump house 3 directly E of reactor.
3 m A-25 Goosequill pond outlet.
1 2.2 6h n z R-10 S.
Platte River at bridge on CO 60.
10.1 z
O C
Food A-27 Fields on SE corner of intersection of WCR 25 4
4.3 g9 Products and WCR 30.
1 9
m A-28 Residence 11399 WCR 40-1/2.
2 5.3 ka m
R-6 Hernandez Produce Stand, Highway 85, 9.6 OM Gilcrest.
ny hd O 2 O
M
> V) 8yeoz e
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