ML041450276
| ML041450276 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/15/2004 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-MT-04-031 ODCM-02.01, Rev 4 | |
| Download: ML041450276 (16) | |
Text
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 1 of 16 I/plr OFFSITE DOSE CALCULATION MANUAL - TABLE OF CONTENTS SECTION PAGE 1.0 RECORD OF REVISION 2
2.0 LIQUID EFFLUENTS 3
2.1 Concentration 3
2.2 Dose 4
2.3 Liquid Radwaste Treatment Systems 5
2.4 Liquid Holdup Tanks 6
2.5 Bases 7
Figure 1 Monticello Nuclear Generating Plant Site Boundary for Liquid Effluents 10 Table 1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 11 Table 2 Radioactive Liquid Waste Sampling And Analysis Program 12 Table 3 Radioactive Liquid Effluent Monitoring Instrumentation 15 OC Final Review Meeting:
Prepared By:
Approved By Plant Manager:
Reviewed By:
Date:
Date:
Resp Supv:
CHEM Assoc Ref:
SR:
2 yrs N
Freq:
CHEM-I ARMS:
ODCM-02.01 Doc Type:
Admin Initials:
Date:
7030 FOR ADMINISTRATIVE USE ONLY 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 2 of 16 I/plr 1.0 RECORD OF REVISION Revision No.
Date Reason for Revision 1
December - 1998 Corrected reference to Table 2.1-1 from 2.1.2.
2 October - 2000 Incorporated Radiological Effluents Tech Specs section 3.8.A and 4.8.A. into document.
3 September - 2002 Revised Actions 2.2.3 and 2.3.3 to standardize documentation and reporting.
4 December - 2002 Table numbering was restarted to reflect 1, 2 and 3 verses 3, 4 and 5 throughout the document.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 3 of 16 I/plr 2.0 LIQUID EFFLUENTS 2.1 Concentration 2.1.1 Controls A.
In accordance with T.S.6.8.D.2, the concentration of liquid radioactive material released from the site (Figure 1) SHALL be limited to ten times the concentration values specified in Appendix B, Table 2, Column 2 of 10CFR20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration SHALL be limited to 2 x 10-4 Ci/ml total activity.
2.1.2 Applicability At all times.
2.1.3 Action A.
When the concentration of radioactive material in liquid released from the site exceeds the above limits, immediately restore the concentration within acceptable limits.
B.
Radioactive material in liquid effluent released from the site SHALL be continuously monitored in accordance with Table 3.
C.
The liquid effluent monitors having provisions for automatic alarms as listed in Table 3 SHALL be used to limit the concentration of radioactive material released at any time from the site to the values given in 2.1.1.A. Setpoints SHALL be determined in accordance with the methods in Section 4.0 of the ODCM.
D.
Report all deviations in the Annual Radioactive Effluent Release Report.
2.1.4 Surveillance Requirements A.
Radioactive liquid wastes SHALL be sampled and analyzed according to the sampling and analysis program of Table 2.
B.
The results of radioactive analysis SHALL be used in accordance with the methods of the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 2.1.1.A.
C.
Liquid effluent monitoring instrumentation surveillance SHALL be performed as required by Table 1.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 4 of 16 I/plr 2.2 Dose 2.2.1 Controls A.
In accordance with T.S.6.8.D.4, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site SHALL be limited:
1.
During any calendar quarter to <1.5 mrem to the total body and to <5 mrem to any organ, and 2.
During any calendar year to <3 mrem to the total body and to <10 mrem to any organ.
2.2.2 Applicability At all times.
2.2.3 Action A.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, document and report IAW ODCM-01.01, Section 2.4.1.C.
2.2.4 Surveillance Requirements A.
Cumulative dose contributions for the current calendar quarter and current calendar year SHALL be determined monthly in accordance with the ODCM.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 5 of 16 I/plr 2.3 Liquid Radwaste Treatment Systems 2.3.1 Controls A.
In accordance with T.S.6.8.D.6, the LIQUID RADWASTE TREATMENT SYSTEM SHALL be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses, due to the liquid effluent from the site would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ when averaged over one month.
2.3.2 Applicability At all times.
2.3.3 Action A.
With radioactive liquid waste being discharged without treatment and in excess of the above limits, document and report IAW ODCM-01.01, Section 2.4.1.C.
2.3.4 Surveillance Requirements A.
Doses due to liquid releases SHALL be projected at least once each month in accordance with the ODCM.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 6 of 16 I/plr 2.4 Liquid Holdup Tanks 2.4.1 Controls A.
In accordance with T.S.6.8.I.3, the quantity of radioactive material contained in each outside temporary tank SHALL be limited to 10 curies, excluding tritium and dissolved or entrained gases.
2.4.2 Applicability At all times.
2.4.3 Action A.
With the quantity of radioactive material contained in any outside temporary tank exceeding the limit in 2.4.1.A. above, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
2.4.4 Surveillance Requirements A.
The quantity of radioactive material contained in each outside temporary tank SHALL be determined to be within the limit in 2.4.1.A. by analyzing a representative sample of the tanks contents at least weekly when radioactive materials are being added to the tank.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 7 of 16 I/plr 2.5 Bases 2.5.1 Liquid Effluents A.
Concentration Control 2.1.1.A. is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. The control provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within (1) the Section II.A design objectives of Appendix I, 10CFR Part 50, to a Member of the Public and (2) restrictions authorized by 10CFR20.1301(e).
The concentration limit for the dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This control does not affect the requirement to comply with the annual limitations of 10CFR20.1301(a).
B.
Dose Control 2.2.1.A. is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10CFR Part 50. Action required by Control 2.2.1 provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept as low as is reasonably achievable. Considering that the nearest drinking water supply using the receiving water is 33 river miles downstream, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141.
The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 8 of 16 I/plr 10CFR50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Revision 1, April 1977. NUREG-0133, October 1978 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
C.
Liquid Radwaste Treatment Systems Control 2.3.1.A. provides assurance that the liquid radwaste treatment system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10CFR Part 50 and design objective Section II.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effluents.
The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Setpoint for these instruments SHALL be calculated and adjusted in accordance with the methodologies and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50.
D.
Liquid Holdup Tanks Restrictions on the quantity of radioactive liquid material contained in tanks are required only for temporary tanks. All exterior permanent tanks are diked to prevent release of their contents in the event of leakage. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the values given in Appendix B, Table 2, Column 2, to 10CFR20.1001-20.2402 at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 9 of 16 I/plr Surveillance requirements for continuous liquid release points are not provided since all Monticello releases are batch type releases.
Radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm setpoints for these instruments will be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm will occur prior to exceeding the limits of 10CFR20. The operability requirements for instrumentation are consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 10 of 16 I/plr Figure 1 Monticello Nuclear Generating Plant Site Boundary for Liquid Effluents
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 11 of 16 I/plr Table 1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements The initial Instrument Calibration SHALL be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using sources traceable to NBS standards. These standards SHALL permit calibrating the system over its intended range of energy and measurement range. For subsequent calibration sources that have been related to the initial calibration SHALL be used.
An initial Instrument Calibration was performed using a liquid reference standard over the systems intended range of energy and measurement range. Solid calibration sources traceable to NBS Standards currently being applied for instrument calibrations were related to the initial calibration. If, in the future, the canal radioactivity monitor is replaced, the following conditions SHALL apply:
a.
Detector response and system efficiency SHALL be equal to or better than the present system.
b.
Footnote (*) SHALL apply./86 Source Sensor Check Check Functional Test Instrument Frequency Frequency Frequency Calibration Frequency Liquid Radwaste Effluent Daily during Immediately Within 3 months prior Within12 months prior Line Gross Radioactivity release Prior to Each to making a release to making a release.*
Monitor Release Liquid Radwaste Effluent Daily during Within 3 months prior Within 12 months prior Line Flow Instrument release to making a release to making a release.
Instruments used in Daily during Within 3 months prior Within 18 months prior Determination of Discharge release to making a release to making a release.
Canal Flow Service Water Discharge Daily Monthly Quarterly Each Operating Cycle*
Pipe Gross Radioactivity Monitor Discharge Canal Gross Daily Monthly Quarterly Each Operating Radioactivity Monitor Cycle **
Turbine Building Normal Daily Monthly Quarterly Each Operating Cycle Drain Sump Monitor Level Monitors for Daily when in Quarterly when in use Each Operating Cycle Temporary Outdoor Tanks use when in use Holding Radioactive Liquid
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 12 of 16 I/plr Table 2 Radioactive Liquid Waste Sampling And Analysis Program Lower Limit of Sampling Minimum Type of Activity Detection (LLD)
Liquid Release Type Frequency Analysis Frequency Analysis (uci/ml)a,e Batch Waste Release Each Batch Each Batch Principal Gamma 5 x 10-7 Tanksb Emittersd I-131 1 x 10-6 One Batch One Batch Dissolved and 1 x 10-5 Each Month Each Month Entrained Gases Each Batch Monthly H-3 1 x 10-5 Componsitec Gross alpha 1 x 10-7 Each Batch Quarterly Sr-89, Sr-90 5 x 10-8 Componsitec Fe-55 1 x 10-6
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 13 of 16 I/plr Table 2 Radioactive Liquid Waste Sampling And Analysis Program (contd)
Notes a.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a real signal.
For a particular measurement system (which may include radiochemical separation):
LLD =
4.66 sb E. V. 2.22. Y. exp(-t) where:
LLD is the a priori lower limit of detection as defined above (as picocurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). Typical values of E, V, Y and t SHALL be used in the calculations.
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
is the radioactive decay constant for the particular radionuclide, and t is the elapsed time between midpoint of sample collection and time of counting.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 14 of 16 I/plr Table 2 Radioactive Liquid Waste Sampling And Analysis Program (contd) b.
A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch SHALL be isolated and then thoroughly mixed to assure representative sampling.
c.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
d.
The principle gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, SHALL also be identified and reported.
e.
Nuclides which are below the LLD for the analyses SHALL be reported as less than the LLD of the nuclide and should not be reported as being present at the LLD level for that nuclide. The less than values SHALL not be used in the required dose calculations. When unusual circumstances result in LLDs higher than required, the reasons SHALL be documented in the Radioactive Effluent Release Report.7/82
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 15 of 16 I/plr Table 3 Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Operable Applicability Action if Minimum Channels not operable Liquid Radwaste Effluent 1
During Release of Liquid radwaste releases may continue for up to Line Gross Radioactivity Liquid Radwaste 14 days provided that prior to initiating a release:
Monitor
- a. At least two independent samples are analyzed in accordance with Table 2.
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
Liquid Radwaste Effluent 1
During Release of Liquid radwaste releases via this pathway may Flow Instrument Liquid Radwaste continue for up to 30 days provided the flow rate is estimated at least every four hours during actual releases. Pump curves may be used to estimate flow.
Discharge Canal Flow During Release of Effluent releases via this pathway may continue Measurement:
Liquid Radwaste for up to 30 days provided the flow rate is
- Open Cycle Mode 1
estimated at least once every four hours during
- Closed/Helper 1
actual releases. Pump curves may be used to Cycle Mode estimate flow.
Discharge Canal Gross 1
At all times Effluent releases may continue for up to 30 days Radioactivity Monitor*
provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a grab sample SHALL be collected and analyzed for gross beta at an LLD of 10-7 µCi/ml or gamma isotopic for principle gamma emitters at an LLD of 5.0 x 10-7 µCi/ml.
- - Indicates monitor provided with automatic alarm.
LIQUID EFFLUENTS Revision 4 ODCM-02.01 MONTICELLO NUCLEAR GENERATING PLANT TITLE:
Page 16 of 16 I/plr Table 3 Radioactive Liquid Effluent Monitoring Instrumentation (contd)
Minimum Channels Instrument Operable Applicability Action if Minimum Channels not operable Service Water Discharge 1
At all times Service water discharge may continue for up to Pipe Gross Radioactivity 30 days provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Monitor*
a grab sample SHALL be collected and analyzed for gross beta at an LLD of 10-7 µCi/ml or gamma isotopic for principle gamma emitters at an LLD of 5.0 x 10-7 µCi/ml.
Turbine Building Normal 1
At all times Liquid sump releases may continue for up to Sump Monitor*
30 days provided that at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a grab sample SHALL be collected and analyzed for gross beta at an LLD of 10-7 µCi/ml or gamma isotopic for principle gamma emitters at an LLD of 5.0 x 10-7 µCi/ml.
Level Monitors for 1
When tanks are in Liquid additions to a tank may continue for up to Temporary Outdoor Tanks use 30 days provided the tank level is estimated Holding Radioactive Liquid during all liquid additions.
- - Indicates monitor provided with automatic alarm.
o./1