ML20136G126
| ML20136G126 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/31/1997 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20136G123 | List: |
| References | |
| NUDOCS 9703170209 | |
| Download: ML20136G126 (23) | |
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i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 1996 January - March 1997 (END OF PROJECT) 1 Public Service Company of Colorado Fort St. Vrain Nuclear Station f
March, 1997 1
9703170209 970311 PDR ADOCK 05000267-R PDR L
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1.0 SUMHARY
- This is the final and concluding Radioactive Effluent Release
. Report for the Fort St. Vrain Nuclear Station. As of July 10, 1996, sufficient radioactive material had been removed from the facility that gaseous and liquid effluent releases were no longer required to be made and controlled in accordance with the Offsite Dose Calculation Manual (ODCM)as approved by the Fort St. Vrain )
- Decommissioning Safety Review Committee (Memo DPT-96-0105 attached to this report) This report summarizes radiological effluent released from the Fort St. Vrain Nuclear Station for the period of January through December, 1996 and January through March 1997, consistent with 10 CFR 50.36a. This information is provided pursuant to the requirements of Section 5.5.2 of the j Fort St. Vrain Decommissioning Technical Specifications (DTS).
This report uses the reporting format recommended by Regulatory Guide 1.21 where appropriate, i The following tables with a supplemental information section are !
included with this report: !
Table Descrintion lA Gaseous Effluents - Summation of All Releases 2A Liquid Effluents - Summation of All Releases 1
2B Liquid Effluents - Batch and Continuous
- 3 Solid Waste and Irradiated Fuel Shipments
} Please note that Tables 1B and 1C (of Regulatory Guide 1.21) have been omitted from this report because all of our gaseous 4
effluents are continuous and assumed to be ground-level releases as opposed to being elevated releases.
Table 4A has also been omitted. The ODCM, copy attached, has been revised to delete the requirement to collect meteorological data. Meteorological data is not needed for calculating dose contributions from effluent releases and it is not needed by the NRC's contractor who evaluates data submitted with the Annual Radiological Effluent Release Reports.
The ODCM relies upon a conservative default value of X/Q for dose calculations instead of using actual meteorological data. The annual average X/Q value of 4.59E-04 sec/m' is specified in the ODCM and in the Fort St. Vrain Decommissioning Plan. This value
- is conservative when compared to actual meteorological data (1989 actual X/O = 1.95E-04) Also, the use of an annual average X/Q for release calculations is consistent with Reg Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," section C.4.
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0 The Fort St. Vrain Decommissioning Technical Specifications and ODCM requirements apply to all reactor produced radionuclides that were identifiable. Individual radionuclides were analyzed and included in this report.
Sample activities that were less than the detection limits were listed as "none detected" and no value was entered into the calculations of the total activities. This resulted in the reporting of values which were representative of the total curies released.
The lower limit of detection (LLD), for the purposes of this report, is defined as the lowest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with a 95% probability of being correct and only a 5% probability of falsely concluding that a blank observation represents a real signal. The LLD values specified in the ODCM are as follows:
Liauid Principal Gamma Emitters 5.00E-07 pCi/ml Tritium 1.00E-05 pCi/ml Gaseous Principal Gamma Emitters 1.00E-ll pCi/cc (Particulate)
Tritium (Gas) 1.00E-06 pCi/cc All samples were analyzed to the LLD concentration limits for nuclides specifically listed in our ODCM, however, those which had values of less than LLD were marked as "none detected". The "none detected" values were not included in the total values for the pathway.
With respect to the total volume of water used for dilution of radioactive liquid effluent, all average diluted concentrations are based on the activity at the unrestricted area. Although this effluent could eventually reach one of two rivers (St. Vrain Creek and South Platte River) which converge approximately one and one-half miles downstream of the plant, no further dilutions were assumed. Additional discussion on river flow is contained in Section 4d of the Supplemental Information Section.
There were no abnormal or unplanned radioactive gaseous or liquid waste releases made during this reporting period.
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Table 3 summarizes the radioactive solid waste shipments for burial made during 1996 and 1997. Since the table states
....for burial or disposal" we have identified all shipments made to a burial site. The summary includes shipments for burial ,
performed by processors and agents from their facilities, in I addition to those made directly from Fort St. Vrain during 1996 <
and 1997. Materials which were shipped to processors and agents '
for volume reduction, incineration, etc. in 1996 and 1997 are not specifically identified in this report. The waste resulting from )
these processes, that was shipped for burial in 1996 and 1997, is '
included in Table 3.
Decommissioning of the radioactive gaseous and liquid waste systems, including the rubber membrane liner holding tank installed in 1994 and described in the 1994 annual report (P-95023) was completed during this reporting period.
There were no changes made to the Offsite Dose Calculation Manual or Process Control Program during this reporting period.
There were no required liquid effluent activity monitors or their l associated recorders inoperable for more than thirty days during !
this reporting period.
Radiation doses resulting from the release of radioactive liquid and gaseous effluents from Fort St. Vrain during 1996 are reported below. Radiation doses were calculated in accordance with the Fort St. Vrain ODCM which is based on NUREG-0472,
" Radiological Effluent Technical Specifications for PWRs", NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", and other inputs from the NRC.
Doses were calculated for a " maximum exposed" individual present at all times of the year at the Emergency Planning Zone (EPZ),
which is a minimum of 100 meters from the Reactor Building exhaust stack, and located in the sector in which all of the activity was calculated to have been released.
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1 The following are the 1996 and 1997 doses: i
'Licuid - 10CFR50 Whole Body 1.80E-05 mrem Maximum Exposed Organ 2.00E-04 mrem i Gaseous - 10CFR50 i
Noble Gas Gamma 0.00 mrem l Noble Gas Beta 0.00 mrem i Iodine, Particulates, Tritium l Adult 1 i Whole Body 0.00 mrem Organ (maximum) 0.00 mrem Bone 0.00 mrem Teen Whole Body 0.00 mrem I Organ (maximum)- 0.00 mrem Bone 0.00 mrem Child Whole Body 0.00 mrem Organ (maximum) 0.00 mrem Bone 0.00 mrem '
- Infant
] Whole Body 0.00 mrem Organ (maximum) 0.00 mrem Bone 0.00 mrem Gaseous - 10CFR20 Iodine, Particulates, Tritium 0.00 mrem All doses are within the limits of 10CFR20 and 10CFR50.
The doses demonstrate conformance with the exposure limit in j 40CFR190 of 25 mrem to the total body, 75 mrem to the thyroid, and 25 mrem to any organ.
, To show conformance with 40CFR190 subpart B, the total curies of
- krypton released from Fort St. Vrain was 0.00 Ci. The 29.78 kev iodine-129 peak is below the minimum detectable energy of our e
detectors. However, waste streams are regularly analyzed i specifically for iodine-129 for compliance with 10CFR61. The results of these analyses have been less than the LLD.
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- An annual land use census was performed as part of the Fort St.
i Vrain Radiological Environmental Monitoring Program. Changes made to environmental sampling locations as a result of the land use census are reported in the Annual Radiological Environmental Monitoring Program Report (Annual Radiological Environmental Operating Report).
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l Effluent and' Waste Discosal Annual Recort Sunclemental Information j Facility: Fort St. Vrain Nuclear Generatina Station Licensee: Public Service Comoany of Colorado
- 1. Reaulatory Limits All results of radioactivity analyses of gaseous and liquid effluent were'used in accordance with the methodology and parameters listed in the Offsite Dose Calculation Manual (ODCM) (DPP-5.4.2) to assure that the concentrations at the point of release were maintained within the regulatory limits contained in the ODCM. These limits ensured the quantity of radiodctive effluent released from the plant was maintained as low as reasonably achievable, and in any event, within the limits of 10CFR20 and in accordance with 10CFR50.
The dose to a member of the public due to I-131, tritium, and radioactive particulates with half-lives longer than eight days in gaseous effluents was limited to:
a) 7.5 millirems to any organ during any calendar quarter, and, b) 15 millirems to any organ during any calendar year.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas was limited as follows:
a) During any calendar quarter to less than or equal to 1.5 millirems to the total body and to less than or equal to 5 millirems to any organ, and, b) During any calendar year to less than or equal to 3 millirems to the total body and to less than or equal to 10 millirems to any organ.
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2.' Maximum Permissible Concentrations (MPC's) l All MPC's used in determining allowable release rates from l the gas and liquid waste systems were those listed in Table l II, Columns 1 and 2 respectively, of Appendix B to 10CFR20. l Public Service Company continues to use Table II of 10CFR20 because we were granted an exemption from the revised 10CFR20 requirements for the duration of the Fort St. Vrain i decommissioning project.
- 3. Averaae Enerav 1
The average energy (E-Bar) of the radionuclide mixture in releases of fission and activation gases was not calculated l or used at this facility. l
- 4. Measurements and Acoroximations of Total Radioactivity a) Fission and Activation Gases Gaseous releases from Fort St. Vrain consisted of water vapor that was evaporated from the surface of the shield water in the PCRV, where it was drawn into the Airborne Contamination Control System (ACCS), and then was exhausted via the Reactor Building ventilation exhaust system. This was a continuous release consisting of tritiated water vapor. This release ,
methodology was acceptable because of the low activity level of the vapor being released from the PCRV. l Batch releases of radioactive gaseous waste were discontinued after March, 1993, when the gaseous waste hold up system was taken out of service.
All radioactive gases were released to the Reactor Building exhaust ventilation system which had a flow rate that could be varied from approximately 10,000 to 35,000 cubic feet per minute.
The gas stream radioactivity was sampled and analyzed l on a weekly basis. In July 1996, after over 3 months !
of concentrations less than 1% of MPC, gaseous ]
monitoring was discontinued. 1 1
b) Iodines The reactor was shut down permanently in August, 1989 and the fuel removed completely in June of 1992 resulting in the elimination of the iodine source term.
Therefore, iodine-131 analysis has been discontinued.
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1 c) Particulates A 2-inch particulate filter was removed and analyzed each week until July 1996. Grcss beta analysis, as well as gamma spectral analysis, was performed to identify and quantify any radionuclides. The quantity of any radionuclides on this filter with half-lives greater than eight days was similarly correlated to total flow during the collection period. After July
, 1996, gaseous monitoring was discontinued as described
. above.
) d) Liauid Effluents
- i. All liquid effluent discharged from the site reached the unrestricted area at the Goosequill Ditch. From that point, the effluent could be diverted to the St.
Vrain Creek via the St. Vrain Slough or, more commonly, diverted to the Farm Pond which is approximately one mile north of the plant site. Outfall from the Farm Pond reaches the South Platte River. Both rivers converge approximately 1-1/2 miles from the plant site.
The average stream flow reported in section 5a of this supplemental report is a summation of both rivers, and was tabulated from data provided by the Colorado Department of Natural Resources in Greeley, Colorado.
Liquid effluent was released from the site using a batch mode from the Reactor Building Sump and the radioactive liquid waste system. Liquid waste from the rubber liner membrane tank was processed through filters and demineralizers, then directed to the Reactor Building sump for eventual discharge through the existing effluent pathway.
A sample of the tanks or sump contents was taken and analyzed prior to each release. These analyses include beta, tritium, and gamma spectroscopy. The results of these analyses, and other analyses as dictated by the gross beta results, were used to determine the maximum release rate from the site. The liquid effluent was diluted with cooling tower blowdown, which runs at or more than 1100 gallons per minute, prior to reaching the unrestricted area. The resulting mixture was sampled during the release period to confirm compliance with regulatory limits.
The liquid effluent from the batch release mode was monitored continuously by a gamma activity monitor.
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r The final liquid effluent release was made on July 3, 1996. After this time, the liquid waste system was dismantled.
All tank level indicating devices, flow monitoring and recording devices, and radiation monitoring equipment were calibrated and maintained at scheduled intervals in accordance with established procedures, e) Overall Errors The overall error associated with determining the total activity released from the site for both gaseous and liquid effluent is estimated to be 17.3 percent. This value is the square root of the sum of squares of counting statistics and associated calibration errors, sampling errors, and tank volume estimates, each considered to be plus or minus 10 percent.
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- 5. Batch Releases 1
a) Licuid l
Number of Batch Releases 7 l i
Total Time Period for l Batch Releases 1.11 E+02 HOURS Maximum Time Period for a Batch Release 4.27 E+01 HOURS Average Time Period for a Batch Release 1.58 E+01 HOURS Minimum Time Period for a Batch Release 4.05 E+00 HOURS Average Stream Flow During Periods of Release of Effluent into a Flowing Stream 3.68E+05 GPM*
- Gallons Per Minute b) Gaseous
- 1. None 10
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- 6. Abnormal Releases a) Licuid Number of Releases Total Activity Released Ci b) Gaseous Number of Releases Total Activity Released Ci 6 l
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. i TABLE 1A .
I EFFLUENT AND WASTE DISPOSAL GASEOUS EFFLUENT - SUMMATION OF ALL RELEASES l
l Estimated Unit Quarter Quarter Total h, 1 2 Error 5 % l A. Fission and activation gases l l
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- 1. None detected B. Iodine
- 1. None Detected C. Particulates
- 1. None Detected D. Tritium
- 1. Total Release Ci 2.96E-01 2.46E-01 1.73E+01
- 2. Average release rate Ci/sec 1.25E-02 1.04E-02 for period
- 3. Percent of % <1 <1 applicable limit l 12
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l TABLE 1A
- . EFFLUENT AND WASTE DISPOSAL l GASEOUS EFFLUENT - SUMMATION OF ALL RELEASES i
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Estimated Unit Quarter Quarter Total 3 4 Error s.
l A. (>ission and activation gases
- 1. None detected.
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- 1. None detected.
! C. Particulates l 1. None Detected 1
D. Tritium i
t I- Total Release
- 1. Ci *ND **N/A 1.73E+01 i 2. Average release rate Ci/sec ND N/A for period i 3. Percent of % 0 0 i j applicable limit 4
None Detected i' i
- Not Applicable - Effluent releases were terminated effective 7/10/96 i
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l TABLE 2A EFFLUENT AND WASTE DISPOSAL )
LIQUID EFFLUENT - SUMMATION OF ALL RELEASES Est.
Units Qtr 1 Qtr 2 Total
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Error A. Fission and Activation Products
- 1. Total Release Ci 3.99E-03 5.82E-03 1.73E+01
- 2. Average diluted pCi/ml 5.26E-08 1.61E-07 concentration
- 3. % of Applicable % <1 <1 Limit B. Tritium
- 1. Total Release Ci 1.82E-02 2.71E-02 1.73E+01
- 2. Average diluted pCi/ml 6.89E-07 1.24E-06 concentration
- 3. % of Applicable % <1 <1 Limit C. Gross Alpha Radioactivity
- 1. None Detected D. Volume of Waste Released prior to dilution Liters 5.18E+04 2.34E+05 1.00E+01 E. Volume of Dilution Water Used During Release Liters 3.42E+07 2.44E+07 1.00E+01 14
TABLE 2A EFFLUENT AND WASTE DISPOSAL LIQUID EFFLUENT - SUMMATION OF ALL RELEASES Est.
Units Qtr 3 Qtr 4 Total Error A. Fission and Activation Products
- 1. Total Release Ci 1.23E-04 *N/A 1.73E+01
- 2. Average diluted pCi/ml 2.73E-08 N/A concentration
- 3. % of Applicable % <1 N/A Limit B. Tritium
- 1. Total Release Ci 8.72E-04 N/A 1.73E+01
- 2. Average diluted pCi/ml 3.84E-07 N/A concentration
- 3. % of Applicable % <1 N/A Limit C. Gross Alpha Radioactivity
- a. None Detected D. Volume of Waste Released prior to dilution Liters 2.76E+04 N/A 1.00E+01 E. Volume of Dilution Water Used During Release Liters 2.27E+06 N/A 1.00E+01 Not Applicable-Effluent releases were terminated effective 7/10/96 15
N TABLE 2B 1
EFFLUENT AND WASTE DISPOSAL LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 1
chlorine-36 Ci *
- 1.07E-03 1.93E-03 iron-55 Ci 2.91E-03 3.88E-03 l 7esium-137 Ci 1.02E-05 1.31E-05 l
1 tritium Ci 1.82E-02 2.71E-02 l
Total for period Ci 2.22E-02 3.29E-02 (above)
Continuous liquid effluent discharges were not made during this reporting period.
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TABLE 2B EFFLUENT AND WASTE DISPOSAL LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released chlorine-: Ci *
- 6.18E-05 **N/A cesium-137 Ci 6.12E-05 N/A tritium Ci 8.72E-04 N/A l
l Total for period Ci 9.95E-04 N/A (above)
Continuous liquid effluent discharges were not made during this j reporting period. '
- Not Applicable-Effluent releases were terminated effective 7/10/96 17
s TABLE 3 EFFLUENT AND W.'.9TE DISPOSAL 1996 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fue2)
- 1. Type of waste Unit Period Est. Tot.
Error, %
- a. Spent resins, filter sludges, m' O.00 E+00 0.00 E+00 evaporator bottoms, etc. Ci 0.00 E+00 0.00 E+00
- b. Dry compressible waste, contaminated m' 1.22 E+02 3.00 E+00 equip, etc. Ci 1.05 E+01 5.01 E-01
- c. Irradiated components, control rods, m i
6.39 E+00 3.00 E+00 etc. Ci 1.70 E-03 1,46 E+00
- d. Other (describe): Waste processed by m' 1.02 E+02 1.00 E+01 vendor Ci 3.83 E+00 1.00 E+01
- 2. Estimate of major nuclide composition (by type of waste) in Curies
Cs-137 59.3% 6.23 E+00 l Eu-152 1.36% 1.43 E-01 H-3 9.03% 9.48 E-01
- c. Ag-110m 54% 9.21 E-04 Co-60 22.7% 3.88 E-04 Ag-108m 23.3% 3.97 E-04
,H-3 0% 0.00 E+00 l l
Eu-152 0% 0.00 E+00 1
H-3 34.4% 1.31 E+00 Cs-137 1.7% 4.66 E-02 Eu-152 24.3% 9.24 E-01 Eu-154 1.5% 5.62 E-02 18 L
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e 3.' Solid Waste Disposition Number of Shioments Mode of Transcortation Destination 18 Public Highway US Ecology, Inc.
Richland, WA 1 Public Highway Envirocare of Utah Clive, UT B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shioments Mode of Transoortation Destination None i
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TABLE 3 EFFLUENT AND WASTE DISPOSAL 1997 SOLID WASTE AND IRRADIATED FUEL SMIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOGAL (not irradiated fuel)
- 1. Type of waste Unit Period Est. Tot.
Error, %
- a. Spent resins, filter sludges, m' O.00 E+00 0.00 E+00 evaporator bottoms, etc. Ci 0.00 E+00 0.00 E+00
- b. Dry compressible waste, contaminated m' O.00 E+00 0.00 E+00 equip, etc. Ci 0.00 E+00 0.00 E+00
- c. Irradiated components, control rods, m' 1.19 E-01 3.00 E+00 etc. C1 1.56 E-07 1.46 E+00
- d. Other (describe): Waste processed by m' 2.26 E+00 1.00 E+01 vendor ci 3.50 E-03 1.00 E+01
- 2. Estimate of major nuclide composition (by type of waste) in Curies
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Eu-152 0% 0.00 E+00 H-3 0% 0.00 E+00
- c. Fe-55 80.5% 1.25 E-07 Co-60 13.3% 2.07 E-08 Ni-63 1.3% 2.10 E-09 H-3 1.5% 2.40 E-09 Eu-152 2.5% 3.90 E-09
- d. Fe-55 83.6% 2.93 E-03 Co-60 10.4% 3.63 E-04 Ni-63 1.8% 6.38 E-05 Cs-137 1.4% 5.05 E-05 Eu-152 2.2% 7.69 E-05 H-3 ,
0.5% 1.71 E-05 20
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- 3. Solid Waste Disposition Number of Shinments Mode of Transnortation Destination 1 Public Highway US Ecology, Inc.
Richland, WA 1 Public Highway Envirocare of Utah Clive, UT l
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shioments Mode of Transnortation Destination None l
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'y m e Interoffice Memo 1 l 4 0 rubiicservice-
- Putsc Sw&* Company of Colomdo l
DPT-96-0105 l i
DATE: July 9,1996
! TO: Ted Borst, DSRC Chairperson FROM: Sam Chesnutt, Project Assurance i
SUBJECT:
Completion of ODCM Requirements This memo documents PSco's position that all requirements of the Offsite Dose Calculation i
Manual (ODCM), DPM-5.4.2, have been satisfied, and that surveillances and other actions '
taken in accordance with the ODCM may be suspended. I i
l The ODCM is required by the Decommissioning Technical Specifications; it provides requirements for gaseous and liquid effluent releases, for reporting, and for the Radiological l
) Environmental Monitoring Program. The Applicability stated in Section 2.0 of the ODCM is j as follows:
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- This procedure is applicable to all routine, planned liquid and gaseous efuent releases l made pursuant to the FSV Decommissioning Technical Specfications and unplanned i liquid and gaseous efuent releases.
- The final liquid effluent release, #559, was completed on July 3,1996, and the liquid effluent release system is being dismantled. All liquids generated in the future will be processed by evaporation or some other means, with contaminants removed as solid low level radioactive waste. Liquids will not be released via the liquid effluent pathway addressed in the ODCM.
- Also, the gaseous effluent release system has been dismantled so that gaseous releascs are no longer made. Reactor Building ventilation exhaust has been monitored for particulates and tritium and nothing has been detected in over three months that would require dose calculation (i.e., concentrations have been less 1% of MPC). Future decommissioning activities will further reduce any remang contamination levels, and will not result in additional gaseous activity.
- Since chere will be no further liquid or gaseous effluent releases from Fort St.
Vrain, the Applicability statement of the ODCM is considered to be satisfied.
ODCM implementing surveillances no longer need to be performed.
The Radiological Environmental Monitoring Program (REMP) is part'of the ODCM that may also be terminated. The REMP essentially confirms the effectiveness of effluent controls by monitoring for radionuclides in the environment. Since effluent releases have been completed, there is no need to continue the REhe.
l FO?sM (C) 850-22416 t
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Dpf-96-0105 Page 2 A final REMP Report (Radiological Environmental Operating Report) and a final Annual Effluent Release Report should be completed and submitted to the NRC.
DSRC concurrence with this position is requested. After DSRC concurrence and by copy of this memo, the Surveillance Scheduler is requested to remove all ODCM implementing procedures (SR-ODC-xx) from the surveillance scheduling data base.
If you have any questions, please contact me at 6201712. '
- A~ Obd Sam Chesnutt
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penc 097 JUL 101996 DSRC Concurrence: i cc: D. Russell T. Schleiger M. Holmes .
J. McCauley M. Block Control Room Operators 1
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