ML19317G432
| ML19317G432 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/11/1973 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| NUDOCS 8003130878 | |
| Download: ML19317G432 (200) | |
Text
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I Docket No. 50-302 EE21.~.I~2.~.' ((.'(( ,7ll] SQp'[
ENVIRONMENTAL TECHNICAL SPECIFICATIONS a L?LLife g? C. i.t$dB ,
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, TABLE OF CONTENTS Pace No.
1.0 DEFINITIONS 1-1 1.1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (ETS) 1-1 1.2 ENVIRONMENTAL PROTECTION CONDITIONS 1-1 1.2.1 Objective 1-1 1.2.2 Specification 1-2 1.2.3 Monitorino Requirement 1-2 1.2.4 Bases 1-3 1.2.5 Environmental Protection Limit 1-3 1.2.6 Point of Discharge (POD) 1-3 1.2.7 AT Across the Condenser 1-3 1.2.8 Unit 3 Mixino Zone 1-3 1.2.9 Emergency Need for Power 1-4 1.3 ' DESIGN FEATURES AND OPERATING PRACTICES 1-4 1.4 ENVIRONMENTAL SURVEILLANCE 1-4 1.4.1 Obj ective 1-4 1.4.2 Specification 1-5 1.4.3 Reportino Requirement 1-5 1.4.4 Bases 1-5 1
.5 Intake Area 1-6 1.4.6 Discharge Area 1-6 f
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c TABLE OF CONTENTS (Cont'd.)
Page No.
~1.5 ADMINISTRATIVE CONTROLS 1-6
- 1. 6 - SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 1-7 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 2-1 2.1 THERMAL 2-1 2.1.1 Maximum AT Across the Condenser 2-1 2.1.2 Maximum Discharge Temperature 2-2 2.1.3 Maximum Heat Rejection Rate 2-4 2.1.4 Rate of Change of Discharge Temperature 2-4 2.1.5 Heat Treatment of Circulating Water System 2-4 2.1.6 Deicino Operation 2-4 2.2 HYDRAULIC 2-5 2.2.1 Intake Velocity 2-5 2.2.2 Discharge Velocity 2-5 2.2.3 Flow Rate Restriction 2-5 2.2.4 Rerervoir Drawdown 2-5 2.3 CHEMICAL 2-6 2.3.1 Blocides 2-6 2.3.2 Corrosion Inhibitors 2-8 2.3.3 Suspended and Dissolved Solids 2-8 2.3.4 H p_H_ 2-8 2.3.5 Other Chemicals Which Affect Water Quality 2-8 11
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.5 TABLE OF CONTENTS (Cont'd.)
Pace No.
P i- '2.4 RADIOACTIVE DISCHARGES 2.4.1 Liould Effluents 2-9 2.4.2 Airborne Effluents 2-15
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.3.0 DESIGN FEATURES AND OPERATING PRACTICES 3-1 3.1 INTAKE SYSTEM 3-1 3.2 DISCHARGE SYSTEM 3-1 f
3.3 CHEMICAL USAGE 3-4 3.4 WATER TREATMENT SYSTEM 3
- 3.5 CHEMICAL - INDUSTRIAL WASTE WATER
, TREATMENT SYSTEM 3-7 3.5.1 Water Treatment Facilities 3-7 3.5.2 Floor and Eaulpment Drains 3-9 3.5.3 Other Discharoes to the Settlino Ponds 3-10
, 3.5.4 Storm Drains 3-10 3.6 PLANT SHUTDOWN 3-11 3 . 7. LAND MANAGEMENT 3-11 3.7.1 Site Management 3-11
, 3.7.,2 Transmission Line Corridor Manacement 3-13 4.0 ENVIRONMENTAL SURVEILLANCE 4-1 4.I NONRADIOLOGICAL SURVEILLANCE 4-1 f'
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TABLE OF CONTENTS (Cont'd.)
Pace No.
6.I SPECIAL PREOPERATIONAL ENVIRONMENTAL STUDY 6-1 6.2 THERMAL PLUME DURING UNIT 3' OPERATION 6-8 6.3 INTAKE VELOCITY DETERMINATION 6-9 6.4 STUDY OF ERROSION IN THE DISCHARGE SYSTEM 6-10 a.
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LIST OF FIGURES No. Page No.
3.1-1 Intake and Discharge Canals 3-2 3.1-2 Detail of the Intake Structure 3-3 3.5-1 Chemical-Industrial Waste Water Treatment System 3-8 3.7-1 Topography Plan and Local Aerial Photograph 3-12 3.7-2 Transmission Lines and Substations - 3-14 4.2-1 Environmental Media an ' Exposure Pathways 4-11 4.2-2 Off-Site Sample Station Locations 4-17 4.2-3 On-Site Sample Station Locations 4-18 5.1-1 Organization for Implementing Environmental Technical Specifications 5-2 5.3-1 Organhation for Independent Review and Auo.' 5-5 6.1-1 Sampling Stations for the Special Pre-operational Environmental Plankton Study 6- 5
'6.1-2 Predicted Temperature Increments Above Ambient in the Discharge Area, Full Tidal Cycle, All Units at 100% Power 6-9 vi
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9 LIST OF TABLES No. Page No.
2.4-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS SCHEDULE 2-12 2.4-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS SCHEDULE 2-18 3.3-1 CHEMICAL USAGE 3-5
- 4.2-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM 4-13 4.2-2 SAMPLE STATION LOCATIONS 4-15 4.2-3 TYPICAL MINIMUM DETECTABLE CONCENTRATIONS 4-19 4.2-4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS THROUGH 1972 4-20 4.2-5 DESIGN OBJECTIVE LIMITS OF CONCENTRATION INCREASE 4-23 5.6-1 REPORTJNG OF RADIOACTIVITY IN THE ENVIRONS 5-12 vii l
FORWARD Pursuant to an Operating License for the Crystal River Unit 3 Nuclear Generating Plant, and in compliance with Section 50.50 of 10 CFR Part, 50, the Florida Power Corporation submits the Environmental Technical Specifications set forth in this document to the U.S. AEC Regulatory Staff for review and inclusion as Appendix B of the Operating License.
These Environmental Technical Specifications include:
(1) Definition of key terms used in the specifications that are not defined in applicable regulations or guides or are not generally accepted terminology.
(2) Specification of: (a) limiting conditions for operation which, if not exceeded, should result in an acceptable environ-mental impact and (b) their associated monitoring requirements.
(3) Specification of those design features and operating practices which could have a significant effect on the environment if changed.
(4) Specification of the environmental surveillance program necessary to assess the impact of plant operations on the environ-ment. The program includes submission of reports to the AEC: (a) on a semiannual basis, and (b) when an observerable effect on certain environ-mental parameters exceeds specified levels.
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( Specification of administrative controls which re-late to organization and management, procedures, review and audit, and records and reports which are instituted in the interest of environmental protection.
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1.0 DEFINITIONS The following terms are defined for uniform interpretation of.the Environ-mental Technical Specifications for Crystal River Unit 3. .
1.1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (ETS)
Refers to all of the information concerning any limitations, conditions and requirements imposed on the applicant which are considered necessary for the protection of the environment. There are 5 types of ETS: (1) Environ-mental Protection Conditions, (2) Design Features and Operating Practices, (3) Environmental Surveillance, (4) Administrative Controls and (5) Special Surveillance, Research, or Study Activities'.
1.2 ENVIRONMENTAL PROTECTION CONDITIONS Limiting conditions imposed on plant effluents which may have an adverse impact on the environment, which are specified in Section 2.0 and which consist of an objective, specification, monitoring requirement and basar.
1.2.1 Objective The plant effluent parameter or operating practice which is to be limited including an identification of the system and location to which the limit pertains and the purpose (s) of the limiting condition including the specific potential adverse environmental impact (s) which the limiting condition is intended to avoid or limit.
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' l .2.2 Specification A quantitative limiting value of a plant effluent parameter or a specific operating practice requirement intended to limit an adverse environmental impact. In the case of radioactive liquid and airborne effluents, specifica-tions of effluent concentrations above which a report is required, are included.
1.2.3 Monitoring Requirement A description of the observations which will be made to provide the informa-tion to show compliance with an Environmental Protection Condition. This description will normally include general descriptions of the measurement methods, sampling methods, location of the measurement, sampling or measurement frequency, accuracy, sensitivity and record keeping. Terms used to specify frequency are defined as follows:
, Once per shift - three times per day, interval may vary from 4 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Daily - Not less than 360 times per year, interval may vary by 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> .
Weekly - Not less than 48 times per year, interval may vary by 3 days.
Monthly - Not less than 10 times per year, interval may vary by 15 days.
Quarterly - Not less than 4 times per year, interval may vary by 30 days.
Semi-annually - Not less than 2 times per year, interval may vary by 60 days.
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'l.2.4 Bases The considerations in developing the specification -d monitoring require-
- _ ment frcm the objective of limiting a potentially ' e environmental impact. Normally these considerations will include the reasons for the i limitation in terms of an environmental impact and consideration of pertinent design capabilities of the system and of special system require-t ments .
, 1.2.5 Environmental Protection Limit (EPL) i Refers to a numerical limitation placed on a plant effluent parameter in Section 2.0.
1.2.6 Point of Discharue (POD)
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The original bulkhead line which can be recognized on maps of the site as approximately the line of the existing outer dike between the intake and discharge canals.
1.2.7 AT Across the Condenser Refers to the average temperature difference between the inlet and outlet of Unit 3 condenser boxes.
1.2.8 - Unit 3 Mixing Zone Refers to the enclosed area of the discharge canal bounded by the eastern end of the canal and the at'.e chase from Units 1.and 2 crossing the canal.
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1.4.2 Specification Environment'al sample description, sampling Imations and frequency, ineasurements to be made on the samples, and measurement quality criteria such as accuracy or minimum detectable concentration. Terms used to specify normal sampling frequency have been defined in Section 1.2.3. In i
unusual circumstances, for example during hazardous weather conditions, the sampling interval may be altered. The reasons for such alterations will be rt. ported in the next routine report.
1.4.3 Reportino Requirement The requirement to report the results of the environmental surveillance program in terms of tirM and in terms of environmental parameter values.
1.4.4 Bases The considerations in developing the specification and reporting require-ment from the objective. These considerations may include pertinent criteria of environmental impact including the normal fluctuations of the value of the environmental parameter in terms of both time and place and the importance to man and/or the ecosystem of the impact.
1.4.5 Intake Area The intake canel and all of the water area south of the north intake dike and within two kilometers of the west tip of the south intake dike.
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' 1.4.6 Discharge Area The discharge canal and all of the water area north of the south discharge
- dike and within two miles of the west tip of the north discharge dike.
1.4.7 Inner Bay Five feet or less in depth composed of a mixture of grassy bottoms, oyster associations, algal bottoms and areas of sand and mud.
1.4.8 Outer Bay The outer basin in which the planktonic ecosystem becomes as important as the bottom ecosystems.
1.5 ADMINISTRATIVE CONTROLS The assignment of responsibilities, organizational structure, review and audit functions and procedures. These administrative controls specify:
(1) action to be taken if an environmental protection condition is exceeded, (2) sampling methods, analytical techniques, etc. to carry out the environmental technical specifications, (3) assurances that plant operating procedures will be in compliance with the environmental protection conditions,
' (4) reporting schedules, (5) the mechanisms for changes in design features and operating practices, in permits, etc. , and in the environmental technical specifications and (6) records retention.
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.1. 6 ' SPECIAL SURVEILLANCE, RESEARCH OR STUDY ACTIVITIES A description of any efforts which are planned, which are single-time, non-repetitive in nature and which have a purpose associated with under-standing, measuring or limiting adverse environmental impacts. The description should include a summary of the objective, the general
- approach to accomplishing the objective, a schedule of significant milestones and completion and a plan for reporting the results to the AEC.
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2.0 ENVIRONMENTAL PROTECTION CONDITIONS 2.1 THERMAL Objective To define the conditions for discharge of the effluent cooling water at the point of discharge to assure compliance with applicable Federal and State regulations to limit thermal stress to the aquatic ecosystem and minimize adverse thermal effects of Crystal River Unit 3 on marine biota. ,
2.1.1 Maximum AT Across Condensers Objective To limit the maximum temperature rise across the condenser during normal operation at all power levels.
Specification The temperature rise across the condenser during normal power operation shall be 21 F or less. If the temperature rise is greater than 21 F for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> corrective action shall be taken to reduce the AT to within the specified limit.
Monitorino Requirement The condenser tamperature rise shall be determined once per shift during power operations utilizing condenser inlet and outlet recording temperature l
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detectors (RTD's) (0-20011 F), the signal from wnich will be input to the control room computer. During power operation, when the RTD's or computer are inoperative, the condenser AT shall be determined once per shift utilizing local temperature indicators on each water box (30-130 t 2 F) .
Bases When Unit 3 is operated at design capacity, the intake temperature will be elevated by a design value AT of 17.1 F. When any one shell of the two twins shelled surface steam condensers are inoperative for maintenance or other reasons, the AT will tend to rise accordingly. Each of the 4 condenser sections will require cleaning every 4 weeks, due to the buildup of marine growth or debris in the pipes and condensers. During extreme climatic conditions, especially during tropical storms, sea grass is up-rooted from the Gulf of Mexico, requiring temporary shutdown of a circula-tor to clean grass and other debris which has accumulated at the intake structure or inside the condenser water boxes. This will cause a temporary increase in the AT across the condenser. Because of these conditions the AT of 21 F for a period in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is specified as a limit.
Monitoring by means of RTD's in the condenser inlet and outlet water boxes
' will provide reliable values of the AT across the condenser.
2.1.2 Maximum Discharge Temperature Objective l
To limit the maximum temperature of the water discharged from the plant to the environment.
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Specification A. The temperature at the POD shall not exceed 106 F for a period in
, excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
B. Whenever the temperature is above 106 F for a period greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, station power shall be reduced to the extent necessary to maintain 106 F at the POD unless there is an emergency need for power.
Monitoring Requirement A. The temperature at the POD will be monitored once per shift during power operations utilizing the manual address of thermistor buoy Station "E" of the Environmental Data Acquisition System. The temperature sensor system has a range of 30 - 110 and an accuracy of 10.2%.
B. When this buoy is inopetative temperatures from other buoys (upstream and downstream) in the discharge canal will be monitored.
C. When the data acquisition system is inoperative the temperature at the POD shall be estimated using prior operating data.
Bases The 106 F maximum effluent temperature is established to assure that the affected area within the receiving waters is minimized.
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2.1.3 Maximum Heat Rejection Rates Not applicable.
2.1.4 Rate of Chance of Discharge Temperature Not applicable.
2.1.5 Heat Treat:nent of Circulatino Water System Not applicable.
2.1.6 Deicino Operations
- Not applicable.
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2.2 HYDRAULIC
. Objective To define the conditions of intake and discharge of cooling water to limit possible adverse environmental impact due to the mechanical forces associated with the flowing water.
2.2.1 Intake Velocity The intake velocity will be measured as described in Section 6.3 to verify the validity of calculated values.
2.2.2 Discharoe Velocity Not applicable.
2.2.3 Flow Rate Restrictions
, Not applicable.
2.2.4 Reservoir Drawdown Not applicable.
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_- 2.3 CHEMICAL Objective
. To define the conditions for release of non-radioactive liquids and solids to the Gulf of Mexico to assure compliance with applicable State and local regulations and to ensure that the releases will not adversely affect public health or the natural environment. All chemical discharges shall be treated to adhere to the Water Quality Standards set forth in the Rules of the Florida Department of Pollution Control Chapter 17-3, Pollution i of Waters, which requires that a 90% organic and inorganic removal factor be applied against the total untreated waste produced by a given plant. The combination of Crystal River Units 1, 2 and 3's chemical
!' waste generation and control fall under this requirement.
2.3.1 Biocides Objective To limit the amount and concentration of residual chlorine discharged to the Gulf.
Specification Chlorination of each of the condenser circulating pipes shall be staggered to prevent simultaneous treatment with chlorine. The maximum concentra-tion of residual chlorine at the POD shall not exceed 0.1 ppm.
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Monitorino Requirement A. The continuous chlorine recorder shall be observed once each day on
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days when chlorination is performed to verify that the residual chlorine does not exceed 1.8 ppm in the individual condenser outlet water boxes.
B. When the chlorine analyzer and/or recorder are inoperative, a sample shall be taken of each affected water box weekly (during chlorination) and analyzed in the Laboratory, using standard methods.
C. The continuous chlorine analyzer shall be calibrated semi-annually.
Bases Residual chlorine has a potentially detrimental effect on the estuary. The chlorine demand of the seawater at Crystal River has a range of 0.6 - 1.8 ppm. Each of the four water box effluent pipes empties into the Unit 3 mix-ing zone. As only one box is being chlorinated at a time an immediate 4:1 dilution occurs. Effectively, this results in water having a maximum chlo-rine residual of 0.45 ppm mixing with an equal volume of water having a minimum chlorine demand of 0.45 ppm and the almost immediate chemical reduction of the remaining chlorine. As each water box is being chlori-nated, a sample is taken from the outlet water box, analyzed for residual ch1crine (free and combined), and the results are recorded on a circular re-corder. Samples are automatically changed by solenoid valves in accordance with the sequence of the chlorine generation system. This system provides a continuous record of chlorine residual in each outlet vvater box.
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2.3.2 Corrosion Inhibitors Not applicable. The industrial waste system insures that the release of corrosion inhibitors will be near zero.
2.3.o suspended and Dissolved Solids Not applicable. The industrial waste system insures that suspended and dissolved solids in the effluent will be near zero. Suspended solid concentrations in the discharge system, due to errosion will be measured as described in Section 6.4.
2.3.4 pH_
Not applicable. The industrial waste system insures that the variation .
about the yearly mean pH of 8.0 of the Gulf waters will be extremely small.
2.3.5 Other Chemicals Which Affect Water Ouality Not applicable. Essentially no chemical releases are anticipated from the plant with the exception of chlorine-chloride from the hypochlorite treat-ment of the condenser cooling water (which is considered in item 2.3.1) and boron. The boron discharge is due to the inefficiency of the condensate demineralizers; the maximum discharge concentration is estimated to be 0.22 p;b of boron per liter of water discharged and the average concentra-tion is estimated to be 0.022 ppb.
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2.4 RADIOACTIVE DISCHARGES Obfective To specify the limits and controls applicable to the release of radioactive effluents to the receiving water and to the atmosphere, to ensure that the releases are as low as practicable and that resulting radiation exposures in unrestricted areas will not exceed a few percent of natural background exposures.
2.4.1 Liquid Effluents Objective To limit the amounts and concentrations of radioactivity in liquid effluent, to provide for appropriate monitoring and to report releases which are significantly greater than design objective values.
Specification
, A. The radioactive release concentrations in liquid effluents from the Unit 3 mixing zone shall not exceed the values specified in 10 CFR 20, Appendix B, Table II, Column 2, for unrestricted areas .
B. The release of radioactive liquid effluents, excluding tritium and noble gases, shall not exceed 10 curies during any calendar quarter.
C. During release of radioactive wastes, the following conditions shall be met:
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- 1. The effluent control monitor shall be set to alarm and automat-
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ically close the waste discharge valve prior to exceeding the limits spec-ified in 2.4. lA above.
- 2. . Liquid waste activity and flow rate shall be recorded during re-lease. If this requirement cannot be met, continued release of liquid effluents shall be permitted only during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> pro-
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vided that during this 48-hour period, two independent samples of each tank shall be analyzed and two station personnel shall independently check valving prior to the discharge.
D. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes, except laundry wastas, prior to their discharge when it appears that the l
projected cumulative discharge over a calendar quarter would exceed 1.25 curies, excluding tritium and dissolved gases. Laundry wastes will be processed in the radwaste system if the gross $-Y-radioactivity concentra-tion leaving the Unit 3 mixing zone exceeds 1 x 10~ pCi/ml.
E. The maximum activity to be contained in one evaporator condensate storage tank that could be discharged directly to the environs, shall not exceed 10 curies, excluding tritium and dissolved gases.
F. When the release of radioactive effluents, excluding tritium and dissolved gases, exceeds 2.5 curies during any calendar quarter, the licensee shall notify the USAEC in accordance with specification 5.6.2.A.
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Monitoring Requirement A. Prior to release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed for gross ( #,y) radioactivity and the discharge concentration will be calculated using the circulating water flow rate at the time of discharge. The amount of major gamma-emitting isotopes released will be determined by analysis in accordance with USAEC Regulatory Guide 1.21.
B. Records shall be maintained of the radioactivity concentrations, volumes before dilution of each batch of liquid effluent released, and average dilution flows and lengths of time over which each discharge oc-curred in accordance with Specification 5.7.
C. The liquid effluent radiation monitor shall be tested and calibrated in accordance with Table 15-3, Rem 23 of the FSAR.
D. The performance of automatic isolation. valves and discharge tank selection valves shall be checked annually.
Bases The specifications are based on the following criteria: (1) The potential ex-posure to the whole body or any organ of an individual in the unrestricted areas shall rot exceed 500 mrem /yr, (2) the design objective is that the annual liquid release, excluding tritium and dissolved gases, should not exceed 5 Ci and (3) the annual average concentration of tritium in liquid wastes prior to release to unrestricted areas should not exceed 5 x 10 bC1/ml.
It is noted that the USAEC analysis which was reported in the Final Environ-mental Statament for Crystal River Unit 3 indicates that a 5 Ci/yr release would result in a maximum individual v!f-site dose of less than 5 mrem /yr.
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, TABLE 2.4-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS SCHEDULE A. Evaporator Condensate Storace Tank Releases Type of Sensitivity of Samolina Frequency Activity Analysis Analysis Each Batch i Gross S,y 10 pCi/ml One Batch / Month Dissolved Noble 10- pCi/ml Gases Weekly Proportional Composite Ba/La-140 10" pCi/ml I-131 Monthly Proportional Composite Gamma Emitters 5 x 10" uCi/ml H-3 10' uCi/ml Gross a 10- pCi/ml Quarterly Proportional Composite Sr-89, Sr-90 10- pCi/ml NOTES:
(1) A proportional sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
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TABLE 2.4-1 (Cont'd)
B. Laundry and Shower Sump Wastes
. Type of Detectable Sampling Frequency Activity Analysis Concentrations
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Each Batch Gross S.y 10 pCi/ml
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Ba/La-140, I-131 10 pCi/ml Monthly Proportional Composite Gamma Emitters 5 x 10" #Ci/ml 2-13 i
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. A. Specification 2.4.1.A insures that the exposure rate wili not ex-ceed 500 mrem /yr in unrestricted areas.
B. Specification 2.4.1.B insures that a quarterly release will not exceed twice the design objective annual release, or in other words that an average quarterly release rate will not exceed eight-times t ce design objective average annual release rate. The factor of eight over the design objective will result in quarterly average concentrations in liquid effluents which are small percentages of the limits specified in 10 CFR Part 20 and also provides operating flexibility so that the public may be provided with a dependable source of power under unusual conditions.
C. Specification 2.4.1.C requires that the liquid effluent release system be designed and operated so that during actual releases, the effluent stream may be stopped if the release concentrations are greater than that which could result in an exposure rate in unrestricted areas greater than 500 mrem /yr.
D. Specification 2.4.1.D requires that the radwaste system be main-tained and operated whenever the projected quarterly release exceeds 1.25 C1, or in other words, whenever the projected average quarterly release rate exceeds the design objective average annual release rate of 5 Ci/yr. This specification insure at the releases will be as low as practicable.
E. Specification 2.4.1.E limits the amount of radioactivity in a single evaporator condensate tank in order to limit the magnitude of an inadvertant release to an amount which is equal to eight-times the design objective release for a single quarter.
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F. Specification 2.4.1.F requires that the USAEC be notified if the release during a calendar quarter exceeds a value which is twice the design objective value. Reporting releases of a factor of two greater than the destgr objective value insures that releases of this magnitude will be of c;i.sne concern and also provides some operating flexibility.
G. Monitoring requirement 2.4.1.A stipulates that radioactive substances and their concentrations in each release will be determined and concentra-tions at the discharge point will be calculated from circulating water flow.
This insures that the essential information for carrying out the specifica-tions will be available.
H. Monitoring requirement 2.4.1.B stipulates that records of concentra-tions and volumes discharged should be available for future reference.
I. Monitoring requirements 2.4.1.C and 2.4.1.D stipulate that periodic calibration and performance checks of essential equipment will be made.
2.4.2 Airborne Effluents Objective To limit the amounts and concentrations of radioactivity in airborne effluents, to provide for appropriate monitoring and to report releases which are significantly greater than design objective values. .
. Specification A. ' The release rate of each airborne radioactive isotope i, except for I-131 and particulates with half-lives greater than eight days, shall meet 2-15
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the requirement that: Qg/mpciR 2.6 x 10 13 , where Q is the measured rate g
of release (C1/yr) of isotope i and mpel is the maximum permissible con-centration of radioactive isotope i as shown in Column 1, Table II of Appendix B to 10 CFR Part 20 (pCi/ml).
B. The release rate, Qg of I-131 and particulates with half-lives greater than eight days will meet the requirement that: Qg R 11. Ci/yr.
C. During release of radioactive gases from the gas decay tanks, at least one of the redundant automatic isolation devices activated by con-tinuous air monitors shall be operating.
D. During release of radioactive gases from the reactor building, the con-tinuous gross gas monitor which activates the automatic purge isolation de-vices will be operating. If inoperable, the containment atmosphere gross gas activity will be continuously monitored.
E. The equipment installed in the airborne radioactive waste treatment system will be maintained and will be operated when the release rates exceed: (a) Two percent of specification 2.4.2. A, or (b) One percent of specification 2.4.2.B.
F. The maximum radioactivity to be contained in one gas decay tank will not exceed 3.5 x 10 Ct.
G. The release :ates, averaged over any calendar quarter will not exceed 16 percent of the 2.4.2.A limit or 8 percent of the 2.4.2.B limit.
H. If the release rates, averaged over any calendar quarter, exceed four percent of the 2.4.2. A limit or two percent of the 2.4.2.B limit then the licensee will notify the USAEC in accordance with specification 5.6.2.A.
2-16
Monitoring Requirement A. The following measurements will be made on the reactor building and auxiliary building gaseous waste streams: (1) The gross noble gas radio-activity will be continuously monitored and recorded to provide Ci per unit volume of gas released, (2) the volume flow rate will be continuously moni-tored and recorded, (3) the radioactivity monitors will be calibrated in terms of Ci per unit volumes of gas or equivalent CPM at least once per quarter by means of a known radioactive source, and (4) at least one vent monitor en each of the effluent release streams will be operating, during power generation.
B. Samples of gas from gas decay tanks just prior to release and from the teactor containment just prior to purge will be taken end analyzed ac-cording to the schedule presented in Table 2.4-2. The release rates shall be based on the sample gross gamma analysis, the waste gas decay tank volumes and pressures, and the containment purge rate. The total release rates of each isotope will be calculated. !
l C. A bypass stream from gaseous effluent streams will be routed con- l tinuously through a series combination of a particulate filter and charcoal filter. These filters will be analyzed for radioisotopes according to the
~
schedule given in Table 2.4-2. The total release rate of I-131 will be cal- I l
culated from the amounts (C1) found on the filters, the sample flow rates j and the gaseous effluent release rates. 1 2-17 l
9
-,, - - . me-g_m --
4 TABLE 2.4-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS SCHEDULE
~
A. Gas Decay Tank Releases Sampling Type of Detectable Sample Type Frecuency Activity Analysis Concentration Gas From Each Tank Individual Gamma -4 Decay Tank Release Emitters 10 #Ci/cc
~
H-3 10 pCi/cc B. Containment Purce Releases Sampling Type of Detectable Samc% Type Frequency Activity Analysis Concentration Gas from Each Purge Individual Gamma Containment . Emitters 10 _4 uCi/cc (3)
H-3 10' pC1/cc C. Condenser Offgas Releases Sampling Type of Detectable Sample Type Frequency Activity Analysis Concentration Gas from the Monthly Individual Gamma Gaseous Emitters 10 uCi/see (3)
Effluent Quarterly H-3 10' pCi/sec Stream D. Reactor Building Exhaust Vent and Auxilliary Buildino Exhaust Vent Sampling Type of Detectable Sampl'e Type Frequency Activity Analysis Concentration (3)
Gas Monthly (I)' I4) Individual y 10 pCi/cc Emitters Quarterly H-3 10- pCi/cc V
2-18 w + . .
TABLE 2.4-2 (Cont'd.)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS SCHEDULE i-Sampling Detectable
- Sample Type Frequency Activity Analysis Concentration
~
Charcoal Filter Weekly I-131 10 pCi/cc
-12
- on Effluent By- Quarterly I-133, I-135 10 C1/cc pass Stream
~
Particulate Filter Weekly Gross $,y 1 x 10 pCi/cc on Effluent By- Weekly Ba/La-140 1 x 10- pCi/cc pass Stream
-II Monthly Gross S, y 1 x 10 pCi/cc Composite -10 Individual y, 1 x 10 CL/cc of weekly Emitters somples Quarterly Sr-89, Sr-90 ' x 10~ C1/cc Composite of monthly samples
-II One weekly Gross a 1 x 10 pCi/cc sample / quarter (1) Analysis shall also be made within one month of the initial criticality and following each refueling process change or other occurrence which could alter the mixture of radionuclides.
(2) For certain mixtures of gamma emitters, it mey not be possible to measure radionuclides at levels near their sensitivity limit when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides that are measurable.
(3) When the iodine or particulate release rate is greater than the release rate given in 2.4.2.F above, the sample shall be analyzed daily until a steady release level has been established.
(4) Applicable for containment only during continuous purging operations during extended maintenance.
2-19
P %; -
. D. The performance of the automatic isolation devices shall be verified annually.
E. Records of the radioactive concentrations and volumes released shall
. be maintained in accordance with specification 5.7.
Bases The specifications are based on the following criteria: (1) The po-tential exposure to the whole body of an individual due to radioactive noble gas isotopes inadvertantly released to unrestricted areas should not exceed 500 mrem, (2) The potential exposure to the critical organ of an individual due to I-131 and radioisotopes in the particulate form with half lives greater than eight days released inadvertently to unre-stricted areas should not exceed 1500 mrem /yr, (3) One design objec-tive is that the release rate of radioactive noble gas isotopes averaged over a yearly interval should result in a dose rate in unrestricted areas of less than 10 mrem per year, and (4) A second design objective is that the release rate of I-131 and radioisotopes in the particulate form with half lives greater than eight days averaged over a yearly interval should result in a dose rate in unrestricted areas of less than 15 mrem per year by inhalation or to the thyroid of a child through the grass-cow-milk-chain.
A. Specification 2.4.2.A requires that the concentration of airborne radioactive isotopes, due to the plant effluents, in any unrestricted area not exceed the maximum permissin.e concentrations specified in 10 CFR Part 20, which insures that the ex p o s ur e ra te w til n ot exceed 500 mrem /yr. Stated mathematically, Q (X/Q)/3.15 x 10k mpci where 1
Qg is the release rate (C1/yr) of isotope i, (X/Q) is the applicable maximum 2-20
,-; w ,
annual average atn;2coheric disgrsion factor in unrestricted areas (sec/m ), 3.15 x 10 in the number of seconda in a year and mpci is the maximum permissible co- , , setion of radioactive isotope i in unrestricted areas as defined in 10 CFR Part 20, Appendix B, Table II, Column 1.
The values of Q7 will be measured as described in monitoring requirement
-6 2.4.2.B. The applicable value of X/Q is 1.22 x 10 sec/m according to the Crystal River Unit 3 Applicant's Environmental Report Docket No.
50-302. ,
Rearranging and including the numerical value of X/Q yields, Q /mpci 2 2. 6 x 10 .
B. Specification 2.4.2.B requires that the concentration of I-131, due to the plant effluents, in any unrestricted area, not exceed 1/233 of the maximum permissible concentration specified in 10 CFR Part 20, which insures that the exposure rate will not exceed 1500 mrem /yr.
Stated mathematically; Q 7 (x/Q)/3.15 x 10 c mpci/233, where Q is the 7
rate of release of I-131 (C1/yr), (x/Q) is the applicable maximum annual average atmospheric dispersion factor in unrestricted areas (sec/in ),
3.15 x 10 is the number of seconds in a year and mpci is the maximum permissible concentration of I-131 in unrestricted areas as defined in 10 CFR Part 20, Appendix B, Te'je :T . Column 1.
Q will be measured as described in monitoring requirement 2.4.2.C. The applicable value of (Y/Q) for any unrestricted area is 1.22 x 10- sec/m as described in Specification 2.4.2. A. The value of mpci (from 10 CFR Part 20) is 1 x 10'I pCi/ml.
2-21
a am 1 _ _ _ _
JSubstitution of tha numerical values and rearranging, yields; Qg R11 C1/yr.
C. Specification 2.4.2.C requires that releases from the waste gas decay tank be controlled so that during certain periodic releases the effluent streams may be stopped if the release concentrations are greater than those which could result in instantaneous exposure rates in unrestricted areas greater than 500 mrem /yr.
D. Specification 2.4.2.D requires that releases from the reactor build-ing are controlled so that during certain periodic releases the effluent stream may be stopped automatically or, in case of monitor failure, man-ually on the basis of air an sample monitor.
E. Specification 2.4.2.E requires that all installed airborne radioactive waste treatment equipment be operating if the release rates exceed the following design objectives values: (1) A release rate of noble gas isotopes which could result in a dose in unrestricted areas of more than 10 mrem /yr. (2) A release rate of radiciodine and particulates which could result in dose rates in unrestricted areas of more than 15 mrem /yr.
This insures that releases will be as Icw as practicab>.
F. Specification 2.4.2.F insures that'an inadvertent release from a gas decay tank rupture would not result in a dose in any unrestricted ares greater than 500 mrem.
The dose, D in rem / year is given by D = (0.25 Ey + 0.23 Eg) Q (X/Q) where x/Q is the applicable atmospheric dispersion factor in unrestricted
-5 areas, a value of 3.04 x 10 sec/m was employed on the basis that the release might occur within a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (See Crystal River Unit 3, FSAR, Docket No. 50-302.) Q is the maximum release in C1, Ey is the y-ray energy per disintegration (MEV) and Eg is the S-ray energy per disintegration. For calculational purposes the release is assumed to be 2-22
mw
~
Xe-133 for which Ey has a value of 0.0728 and Eg has a value of 0.126 MEV. Rearranging the above equatien and inserting the numerical values, including 0.5 rem / year for the maximum value of D, yields, 5
Q R 3.5 x 10 C1.
G. Specification 2.4.2.G requires that the release rates, averaged over any calendar quarter, not exceed eight times the design objective values.
The factor of eight over the design objective will result in quarterly average airborne concentrations in unrestricted areas which are small percentages of the limits specified in 10 CFR Part 20 and also provides operating flexibility so that the public may be provided with a dependable source of power under unusual conditions.
H. Specification 2.4.2.H requires that the USAEC be notified if the release rates, averaged over any calendar quarter, exceed twice the design objective values. Reporting releases of a factor of two over the design objective valt es will insure that releases of this magnitude will be of genuine concern and also provide some operating flexibility.
I. . Monitoring requirements 2.4. l. A, 2.4.1.B, and 2.4.1C insure that the essential information with which to carry out the specification will be available.
J. Monitoring requirement 2.4.1.D-stipulates that periodic tests of automatic isolation be done to demonstrate their ability to perform.
K. Monitoring requirement 2.4.1.E stipulates that records of concentra-tions and volumes released should be available for future reference.
2-23
_ .m. r _ . .
3.0 DESIGN FEATURES AND OPERATING PRACTICES 3.1 INTAKE SYSTEM Intake water is delivered through an intake canal which is 150 ft. wide, has a depth of 15 ft below mean low water, and extends into the Gulf about 3 miles but is dredged for an additional 3.5 miles into the Gulf. A spoil bank extends into the Gulf for a distance of 6.5 miles and is continuous for the first 4.5 miles except for a gap 3 miles offshore. This spoil bank prevents recycling of heated effluent. The layout of the intake and discharge canals is shown in Figure 3.1-1. At the plant intake, cool-ing water passes through a coarse trash rack (4-in. wide vertical spacing) and then through a traveling screen with openings of 3/8 in. The screens are cleaned by high pressure water sprays, with accumulated debris being slutced into a retention basket by means of a water jet. This debris is routinely removed and buried on-site. The design of the intake structure is shown in Figure 3.1-2. Following the screens, the water enters four pumps (170,000 gpm each) . Four 90-in. (inside diameter) concrete pipes
~
transport the water to rectangular flumes which are 6 ft. 6 in. x 7 ft. 6 in.
3.2 DISCHARGE SYSTEM J
. 4 From the condenser the cooling water passes through ducting similar to that described for the inlet, and then into the discharge canal (Figure 3.1-1),
where the water from Unit 3 will mix with that from Units 1 and 2. Transit time of the heated water from the condenser outlet to the point of mixing with discharged water from Units 1 and 2 is approximately 6 minutes. The combined flow from the three generating plants is transported to the Gulf via 3-1 1
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wide and dredged to 10 ft. below mean low water. A spoil bank or dike extends a further mile from the shore into the Gulf. Water velocity in the discharge canal has been calculated to be 2.4 ft./sec. Transit time from the ger.erating plants to the discharge point will be approximately 1 hr.
At the discharge point, the heated cooling water mixes with water from the Gulf.
3.3 CHEMICAL USAGE Table 3.3-1 presents the estimated amounts of chemicals to be used on site and that will be ultimc*ely discharged from the plant. The industrial waste-water collection pond will service these wastes, except for the lime sludge (which is handled as described in Section 3.5). Percolation from the ponds will provide separation and treatment. Test wells are located around the ponds for testing groundwater to assure compliance with applicable State of Florida water quality standards.
3.4 WATER TREATMENT SYSTEM i With the exception of sea water for condenser cooling, all water used at the Crystal River Plant comes from Florida Power Corporation shallow wells located about four miles east of the plant. In 1970,161,000,000 gallons were drawn from these wells. All of this water is processed through the plant water treatment system lime softener and anthracite filters before use. This " treated water" is the potable water used for all plant functions except steam generator make-up.
l 3-4 c
. n.w.~ .;. ,
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- TABLE 3.3-1 CHEMICAL USAGE Chemical Source or Purpose Annual Usaae
' ~'
Phosphate (PO ) Boiler Blowdown 895 lbs.
4 Caustic Soda (NaOH) Demineralizer Regenerate 593,050 lbs. !
-Hydrazine Oxygen Scavenger 237 lbs.
Lime' Water Softening 400,000 lbs. '
i' NaZnPO 4
Water Softening 3,338 lbs .
Cyclohexamine Condensate pH Control 220 gal.
Sulfuric Acid (H2SO4) Demineralizer Regenerate Units 1 and 2 120,120 gal.
, Unit 3 Makeup Demineralizer 36,500 gal.
Unit 3 Condensate Polishing
- Demineralizer 243,670 gal.
Ammonia Boiler Blowdown, Condensate Polishing 730 gal.
- POW #671, Polyelectrolyte Coagulant Aid 91 lbs.
Sodium Hypochlorite Water 24,000 lbs .
, Dilute Hydrochloric Acid (hcl) Boiler Cleaning 15 ,000' gal.
i - Ethylene Diamino Tetracetic -
i Acid (EDTA) Acid Cleaning 8,000 gal.
. Rodine 31A Acid Cleaning (Stabilizer) 20 gal.
Synthetic Insulating' Fluids
-(Askarels and Intertconi and Normal Transformer Oils : Transformers < 100 gal.
CS (Calgon Corrosion Closed Cooling System Inhibitor Control) (Units 1 and 2) 1,000 lbs.
L 3-5 c.
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Demineralizers are used for purification of make-up water to the boilers
~
or steam generators. The " treated water" from the lime softener is processed through a series of cation, anion and mixed-bed units to remove dissolved mineral salts and through degasification equipment to remove dissolved gases.
3.5 CHEMICAL - INDUSTRIAL WASTE WATER TREATMENT SYSTEM The chemical-industrial waste water treatment system will collect and transport all water wastes to the percolation / evaporation ponds. Each component of the system is described in the following paragraphs; the system is shown diagramatically on Figure 3.5-1.
3.5.1 Water Treatment Facilities A. Well Water Pretreatment Lime Sludge To eliminate discharges from this source, a closed cycle system is used. The Lime sludge will be collected and diverted to dewatering facilities which will remove the solids for disposal without discharge into the circulating water and recycle the clarified water for other plant uses. The facility is sized to handle full flow from the lime-softner.
The chemicals used in the lime softener include dehydrated lime, coagulant aid, and sodium hypochlorite. The sludge formed as a result cl the addition of these chemicals to the well water is primarily calcium carbonate and magnesium hydroxide. The sludge from the lime softener is discharged to a conveyorized settling tank where solids are separated 3-6
into movable containers and the liquor is recycled back into the softener.
The backwash from the anthracite filters is pumped into a 75,000 gallon neutralization tank located at the rear of the water treatment building and from there it is pumped to evaporation-percolation ponds. Operation of the lime softener is not continuous, but rather on a demand basis which is dependent on power station requirements.
B. Water Treatment Demineralizer Waste Chemicals The system collects the chemical waste solutions from the demineralizer plant in a neutralizer tank. These wastes are then discharged into the settling ponds.
Approximately every four days, the resins in the ion exchange units must be regenerated. There are about 10,000 gallons of waste chemical colutions produced during each regeneration. These wastes are pumped tc the neutralization tank and subsequently to the evaporation-percolation ponds.
C. Water Treatment Demineralizer Backwash and Rinse The water used for backwashing and rinsing during all domineralizer regeneration operations is placed in the neutralizer tank and then discharged into the settling ponds.
3-7 t- - -
emD POWER PLANT EQUIPMENT :
DRAINS Il SAMPLE POINT
_f HOLDING POND NO.1 POWER PLANT _
FLOOR DRAINS Il WATER TREATMENT DEMINERALIZER r OVERFLOW WASTE DRAINS BOILER AND AIR O NT HEATER WASH DRAINS - I HOLDING POND NO. 2 g SOILER 8 LOWDOWN I
LIME SOFTNER S'. IDSIN SOLIDS D- tSFOR BLOWDOWN AND :
CEPARAROR 1
WASTE DPAINS D A SAL c
il CLARIFIED WATER RECYCLED TO SOFTNER ir Figure 3.51 Chemical-Industrial Waste Water Treatment System l 3-8 l
3.5.2 Floor and Equipment Drains Drain piping is routed to sumps to collect plant and equipment drains.
The waste water collected in the sump is pumped to the settling ponds.
All floor and equipment drains are kept isolated from roof and yard drains .
A. Lubricating and Hydraulic Oil Spillage from Mechanical Equipment Quantities are small and will be cleaned up by plant personnel and not flushed down floor drains.
B. Fuel Oil Spills at Fuel Oil Heaters, Pumps or Burners These are minimized by isolating (diking) the floor areas around the heaters and pumps to contain any spills in that area. Also, oil sumps and pumps are provided at various locations to pump oil drips back into the fuel oil-piping system.
1 C. Cleaning Solutions Such materials used for regular plant cleaning, floor washing, equipmant cleaning, etc., go to the drains as does the dirt, dust, flyash and other assorted contaminants.
3-9
... , ,_. - ._l
9 3.5.3 Other Discharaes to the Settlino Ponds A. . Chemical Cleaning of Boiler Internals If the steam generators require chemical cleaning these solutions and the rinse water used following boiler chemical cleaning is pumped to settling ponds.
B. Steam Generator Blowdown This water is transferred from the blowdown tank to the settling .
ponds.
3.5.4 Storm Drains The pollution potential from storm drainage is reduced by land-scaping, grading and " plant keeping" which assures that the storm water runoff will be kept as natural as possible.
The yard drains are reconstructed so that they will have no sources of plant pollution connected to them. The areas around the transformers
~
are recognized as a possible source of oil from a transformer tank rupture; therefore, dikes are constructed in these areas which will trap any oil that may be lost. The roof drains collect rainwater and conduct it directly to the yard drain system. These drains are kept separate from the floor or equipment drains to prevent entry of contaminants from the plant, and the rainwater from the roofs is discharged into the discharge canal with the yard drains.
l 3-10 l l
i l
I
~
S 3.6 PLANT SHUTDOWN There are three units on site (Unit 1, 387 MWe, fossil-fired: Unit 2, 510 MWe fossil-fired; a'nd Unit 3, 855 MWe, Nuclear) and all use the i
same once-through condenser cooling water system. Planned or emergency shutdown of the nuclear unit (or any of the three) will not result in any serious therml gradient. If all units were operating at peak power,
. outage of Unit 3 would cause a temperature decrease of 8.8 F at the POD. The probability that all three units would be shut down simultaneously is so small that protective action is not considered neces sary.
3.7 LAND MANAGEMENT This section describes the plans and practices the licensee shall use in managing and maintaining the site and transmission corridors. Every effort shall be made to minimize the environmental effects of land use.
3.7.1 Site Nanagement Original acquisition of a plant area substantially in excess of that i
required for structures or construction has resulted in the preservation of a substantial buffer zone containing lands, salt marshec and small tidal i
, creeks which are protected against encroachment from any other coastal development. Hunting'is prohibited, thus providing a preserve for the wildlife existing in the area. Figure 3.7-1 indicates the approximate percentage of land use cleared for primary construction. The licensee will provide landscaping after final heavy construction.
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, The licensee does not plan to develop any of the land area for recreational purpos es . Preservation of the area in its natural state with its salt marshes, salt swamps, fresh water swamps, hammocks, grass flats, and other features is considered to be a higher priority. The site was designated as a Bald Eagle sanctuary in 1964 under a cooperative agree-ment between FPC and the Florida Audubon Society.
The offshore marine environment does have recreational potential. During the cooler winter months, extensive fishing now occurs in the discharge canal of the existing Crystal River plants where the warmed water attracts sport-fish. Sport-fishing in the area should increase over the coming 40 years . 3.7.2 Transmission Line Corridor Management The plant was built at an established power plant site already occupied by two fossil-fuel generating plants and located on the transmission system of the State of Florida as illustrated in Figure 3.7-2. Some additional transmission lines were required as a result of the construction of Unit 3. The new lines are 500 kV and extend from the Crystal River site about 53 miles to the Central Florida Substation near Leesburg-and about 72 miles to the Lake Tarpon Substation near Tarpon Springs. In some areas, trees were removed along these right-of-ways. The power lines have the normal agricultural land. There are no unique scenic views along these transmission corridors. 3-13
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l Both new transmission lines (500 kV) are within existing power line case-ments already partly occupied by 230 kV lines. The power lines leave the plant along the access road and railroad spur on Florida Power Corporation property. The 500 kV lines occupy aomewhat less than 150 ft. of the existing transmission corridor. Each of these major corridors runs through mixed terrain including forest, farm land, commercial, rural residential and uninhabited areas. Compatible uses of transmission corridors by the' local residents in the past have been encouraged. Although each case is handled on an individual basis, no change in past company actions in this area is expected. b a 3-15 [. L_ '
4.0 ENVIRONMENTAL SURVEILLANCE 4.1 NONRADIOLOGICAL SURVEILLANC_E The estuary has been exposed to the influence of the operation of Units 1 and 2 for approximately seven (7) years. During this time, tae systems in the area have adapted to this influence. Research is currently determining the exact nature of the new stabilized conditions relative to control areas adjacent to the plant site. Thf re.tearch consists of system modelling with measurements of biomass, goductivity, respiration and diversity in all major compartments. The information derived will also serve ae a baseline for comparison with the data taken after Unit 3 becomes operational. The purpose of a post-operation surveillance program is to determine any significant effects of the operation of the power plant, particularly unpredicted and catastrophic changes. The present program has been designed to yield this information. It is expected that there will be a period of adjustment of the ecosystem concurrent with Crystal River Unit 3's initial operation. This will be a localized perturbation limited to a portion of the inner bay. Its causes are expected to be from effects associated with the higher water velocity as well as the temperature increase. Any eccaystem which experiences a change in its environment will undergo a period of adaptation unless catastrophic conditions occur. With the small changes anticipated with the addition cf Unit 3, no catastrophic effects are
~
4-1
- ~
v. expected. At any rate, any changes in the environmental conditions of a system will normally cause it to oscillate. An example of the oscillation of a hypothetical system's productivity is shown below, r Time to Perturbation
! r-Time to Minimum l r- Approximate Time to Stabilization i I 1 I l
i l i Stabilized Level I 1 3 i Productivity 5
--------- Initial Level
_ _ _ _ - - . ---- Minimum Level Time : In this particular system the final stabilized level is higher than the initial level nd is only obtained after a period of stabilization and after going through a suppressed level after the initial perturbation. The recognition of this type of potential response is obviously important in considering any surveillance program. The models of the sytems involved at Crystal River along with the data available indicate that the approximate time to stabilization should not exceed one year. Therefore, the time frame for the surveillance programs allows one year of monitoring to determine the transient response that the systems are experiencing. An additional year of monitoring is planned to indicate the new stabilized level. If the second year's data indicate that the systems have not approached stabilization, the monitoring programs 4-2
w should be extended an additional year. It is not expected that the intensive surveillance should be necessary beyond three years. In addition to the two-year programs designed to determine how the systems have responded to the perturbations, an on-going program has been designed to obtain a diagnositic view of the condition of the environm ent. This program consists of a number of simple measurements which will indicate any major changes in the system. The areas in which intensive monitoring will be performed until stabili-zation occurs are:
- 1. Thermal plume model verification,
- 2. Benthos in discharge area,
- 3. Marsh grasses, and
- 4. Impingement on intake screens.
4.1.1 Therma 1 Plume Model Verification Objective
. The objective of this program is to verify previous calculation which predicted the size and location of the effluent thermal plume.
Specification Salinity, temperature, and depth measurements will be made in the discharge area under all tidal conditions. Isotherm contours will be mapped and compared with predicted values. Two surveys will be made during the first year of operation: one with winter conditions and one with summer conditions. I 4-3
Reportina Requirement Results of the data gathered in this program will be reported in accordance with 5. 6.1. In addition, any isotherm which exceeds the predicted area by 30 percent will be reported as specified in Section 5.6.2. Bases A full spectrum of thermal conditions is included during the summer and winter measurements under all tidal conditions. The limit of 30 per-cent was established because this is the maximum expected error of the analytical program due to uncertainties caused by solar back-radiation. 4.1.2 Benthos in Discharge Area Productivity, respiration, biomass and diversity of the benthic system in the inner bay region. Objective The objective of this program is to determine the condition of the area directly affected by the thermal plume. Specification Post-operational monitoring will be conducted quarterly for two years. Diversity and biomass of the benthic system in the area adjacent to and north of the discharge canal will be measured on a seasonal basis for two years after plant operation begins. Samples will be taken by harvesting i e i 1 4-4 l l
. . = .
4 quadrats, by sediment cores, and by venturi pumps. The number, frequency and location of samples to be taken will be determined from a statistical analysis of the research presently being conducted in this area. Productivity and respiration of the system will be determined by the methods currently employed in the modelling work. Reportino Reguirement Any changes in biomass, productivity or respiration beyond 2a of that measured during preoperational monitoring will be reported in accordance with 5.6.1. Bases In the discharge area adjacent to the canal the productivity, respiration and biomass should increase due to an increased temperature of the cooling water. If the opposite occurs and any of these parameters , j decrease below 2a of that measured during preoperational monitoring, the systems should be investigated for catastrophic results. l 4.1.3 Marsh Grass ! l l Objective l l The purpose of this program is to measure the condition of the salt marsh adjacent to the discharge area. 4-5 l i
Specification The biomass, productivity, and respiration of the salt marsh shall be measured on a quarterly basis. -Quadrats will be harvested to determine biomass and productivity. Gas metabolism techniques will be used to determine productivity and respiration if the necessary equipment is available for use. Reportino Requirement - All of the parameters monitored in this program should increase with the addition of thermal energy. In the event that any parameter measured decreases beyond 2a of the value measured in the preoperational monitor-ing program a report will be submitted to the AEC 'as specified in Section 5.6.2. . Bases The metabolism of the marsh grass should increase with increasing temperature. Any decrease indicates a breakdown of structure. A decrease of greater than 2a should indicate a trend and thus is worth additional considerations . 4.1.4 Impincement on Intake Screens Objective 1 The purpose of this progtam is to determine the quantity of impinged fish on ~ the intake screens to compare with preoperational data. - 4-6 m .= yme e. . M$ -. --.M M +
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Specification The fish collected in the trash racks adjacent to the intake screens of Units I and 2 and Unit 3 will be sampled on an hourly basis for 24 consecutive hours once weekly. This program will be extended for one year after operation of Unit 3 begins. Samples will be sorted according to species, length, and wet weight. Reportino Requirement
' Any daily sample with biomass greater than 40 kg will be reported to the AEC as specified in Section 5.6.2.
Bases Preoperational data indicate that the average normal expected catch is approximately 20 kg. Any samples greatly in excess of this value should be reported. 4.1.5 General Ecological Survey Obj ective 1 In addition to the program outlined for specific areas, a generally comprehensive series of measurements is planned to indicate the condition of the environment. These measurements were designed to reveal changes which might occur and would be used to indicate areas requiring more detailed investigation. 4-7
Specifications The areas to be monitored are:
- a. Outer bay (plankton-dominated area) . The percent of saturation of oxygen will be measured at dusk and dawn twice monthly.
In addition, a tow with a 202 g zooplankton net will be made semi-annually. Species diversity will be determined,
- b. Canals . The percent of saturation of oxygen will be measured at dusk and dawn twice monthly at the point of discharge.
- c. Intake screens. The screen-wash racks will be monitored visually daily to determine any abnormal catches (greater than 40 Kg).
- d. Inner bay. Quarterly tons by a man in a glass-bottomed boat to observe the general condition and percent cover of the grasses will be made. These tows will be along a transect along a radial from the plant.
- c. Oyster reefs . Counts of the species diversity within a quadrat on the reef will be made quarterly,
- f. Marsh grasses. Stem counts of grass within a quadrat will' be made quarterly. This measurement will be correlated with biomass.
In addition, the number of crab holes within a quadrat will be observed as a biomass indicator. 4-8
s
. Reportina Recuirement Reports will be furnished in accordance with Section 5.6.1.
Bpses The parameters to be measured were chosen to indicate general trends in the conditions of the environment and should be used to indicate areas where further investigations may be warranted from time to time. 5 I l 4-9 r
~
4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING The liquid and airborne radioactive effluents will be monitored, controlled and audited as specified in Section 2.4. The radiological environmental monitoring program will provide information which can be used to assist in assessing the type and quantity of radiation exposure in unrestricted areas resulting from plant operation. Environmental media which are sampled and analyzed for radioactivity are shown by the two diagrams on Figure 4.2-1. Each box in the diagrams contains the name of an environmental media which is sampled. The upper diagram shows the critical pathways; the lower diagram shows the other monitored pathways. Preoperational radiological environmental monitoring programs, to establish baseline environmental concentration values, were initiated in mid-1970. Results from these programs have been reported.* One program was operated by the State of Florida Department of Health and l Rehabilitative Services; another program was operated by the University ! of Florida. Measurements of gross beta concentrations in air particulates at a location in St. Petersburg, Fla. , have been made by the Pinellas County Health Department.
- Florida Power Corporation, " Environmental Status Report July-August-September 1970", pp. 4-5, pp. 41-52.
Florida Power Corporation, " Environmental Status Report October-November-December 1970", pp. 4-6, pp. 48-72. Florida Power Corporation, " Environmental Status Report January-February-March 1971", pp. 4-6, pp. 42-65. 4-10
1 AIF80RNE RELEASES LIQUID RELEASES ir l ' I AIR 'j SE A WATER l l F 4 l SURFACE WATER l EXTERNAL 4 , RADIATION l POTABLE WATER l lMl Kl C If MAN CRITICAL PATHWAYS AIR 80RNE RELEASES LIQUlO RELEASES l AIR l f SEAWATER l t t t 4 i 6 6 6 FORAGE D XTERNAL AQUATIC AOUATIC PRECIPITATION , *-- SEDIMENTS . , CROPS RADIATION PLANTS ANIMA L'. I , h I '<! GROUND [ MILK l f - WATER POTABLE WATER O ER
~
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h MAN OTHER MONITORED PATHWAYS Figure 4.2-1 Environmental Media and Exposure Pathways 4-11
56-a i Florida Power Corporation, " Environmental Status Report April-May- ! June 1971", p. 5, pp. 61-79. Florida Power Corporation, "Envircnmental Status Report July-August-September / October-November-December 1971", p. 7, pp. 62-93. Florida Power Corporation, " Environmental Status Report January , February, March / April, May, June 1972", pp. 7-8, pp. 32-61. Florida Power Corporation, " Environmental Status Report, July, August, September 1972", p. 7, pp. 90-107. The overall program is outlined on Table 4.2-1. Sample station locations are described on Table 4.2-2 and shown on maps on Figures 4.2-2 and 4.2-3. Typical minimum detectable concentration values are given on Table 4.2-3. A tentative and partial summary of the preoperational surveillance results is shown on Table 4.2-4; a final summary in this format will be provided after the conclusion of the preoperational program and prior to reactor s tart-up. This summary includes median values of the observed environ-mental concentrations and 95 percentile values (i.e. , values which exceed 95 percent of all the comparable measured values) . The median values will be taken as the preoperational baseline concentrations. The 95 percentile values indicate the random treguency of high measured values during the preoperational program and also the random frequency of high values which can be expected during operation if the plant operation contributes negligibly to the environmental radioactivity. These 95 percentile values will be used during operation to assess the probability ( that any observed high concentration value is due to random fluctuations ! in measurements rather than to a true increase in environmental concentra-i tions . 4-12'
TABLE 4.2-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Sample Sample Sampling / Collection Analysis Tvoe Stations Frequency Routine Air C04, C07, C18 Continuous / Weekly Gross $ and I-131 C24, C40, C41 weekly, y-spectral on monthly composite External - C04, C07, C09, Continuous / Monthly TLD Radiation Ci8, C24, C40, C41, C42, C43 Precipitation C04, C24, C40 Continuous / Monthly Gross g, H-3, y-spectral analysis Sea water C01, C09, C13, Monthly H-3, y-spectral C14 analysis, Sr-89, Sr-90 on C14 and on others if detected in C14 River water C15 Quarterly Gross S, H-3, y-spectral analysis Ground C44 Semi-annual Gross g, H-3, water y-spectral analysis Potable - C07, C10, C18, Quarterly Gross S, H-3, water C24 y-spectral analysis Bottom C01, C09, C14H, Quarterly y-spectral analysis , sediments C14M, C14G Sr-89, Sr-90 on C14 and on others if detected in C14 4 Crabs C29, C30 Semi-annual y-spectral analysis , Sr-89, Sr-90 4-13 4
^
TABLE 4.2-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM (Cont'd.) Sample Sample Sampling / Collection Analysis
~
Type Stations Frequency Routine Oysters C29, C30 Semi-annual y-spectral analysis , Sr-89, Sr-90 Shrimp C28 Semi-annual y-spectral analysis , Sr-89, Sr-90 Carnivorous C29, C30 Semi-annual y-spectral analysis , fish Sr-89, Sr-90 Herbivorous C29, C30 Semi-annual y-spectral analysis , fish Sr-89, Sr-90 Marine C29, C30 Semi-annual y-spectral analysis , plants Sr-89, Sr-90 (macro-algae and submerged grasses) Milk C05 Monthly y-spectral analysis , Sr-89, Sr-90, I-131 Small C45 Semi-annual y-spectral analysis terrestrial animals Vegetation C05, C25, C40, Semi-annual y-spectral analysis (grasses) C41 Food crops C19 Annual y-spectral analysis ,
.(citrus) Sr-89, Sr-90 l
4-14
TABLE 4.2-2 SAMPLE STATION LOCATIONS Station Distance from Direction from Number Location plant (miles) plant C01 Levy County Park 7.2 NNE West end State Road 40 C04 Sec. 7T17 State Road 17E 6.9 NE State Park Old Dam on River C05 Holland Ranch 2.3 NE S24T24SR16E C07 Crystal River Public 7.5 ESE Water Plant C09 Citrus County Park 5.0 SSE END SR44 R16 ET 18S C10 Indian Waters Public 4.9 SE Water Supply C13 Mouth of Intake Canal 2.6 WSW C14
- Discharge Canal 1.4 W C15 Withlacoochee River 5.9 N Yankeetown Dock Isaac Walton Lodge C18 Yankeetown City Well 5.8 N C19 NW Corner SR448 12.6 NE C24 City of Inverness 25.3 SW Public Water Supply
, 4-15
TABLE 4.2-2 SAMPLE STATION LOCATION (Cont'd.) Station Direction from Direction from Number Location plant (miles) plant C28 Ralston Purina Research 0.5 W Facility between Intake and Discharge Canals C29 Discharge Area 2.0 W C30 Intake Area 3.0 WSW C40 On site near N.E. 1.5 ENE Boundary at excavated pond and pump station C41 On-site meteorological 0.4 SSW tower C42 Mid-way out discharge 1.2 W canal on S. side C43 S.E. corner Holland 1.6 NW Ranch C44 , On-site well supply to 0.2 E plant softener C45 On-site along main 1.3 ENE access road (a) C14H refers to a station at the head end of the discharge canal; C14M refers to a station midway between the ends of the canal: C14G refers to a station at the Gulf of Mexico end of the canal. 4-16
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- e ,x TABLE 4.2-3 TYPICAL MINIMbM DETECTABLE CONCENTRATIONS Gross B In air 1 pCi/m By Means of y-Spectral Analysis Co-58 10 pCi/l*
Co-60 10 pCi/l Ba-140 10 pCi/l Cs-134 10 pCi/l Cs-137 10 pCi/l Zn-65 20 pCi/l Mn-54 10 pCi/l Tritium Unenriched 200pCi/l Enriched 30 pCi/l Strontium Sr-89 5 pCi/l Sr-90 2 pC1/1 I-131 In air 0.06 pCi/m In milk 0.5 pCi/l External Radiation 5 mrem /yr.
- Units of pCi/l pertain to media of unit (Ig/ml) density 4-19 l
h
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TABLE 4.2-4 I
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 Preoperational Concentrations Environmental Media _ Nuclide Median Value 95 Percentile Value Water, Potable Gross (a) 19. pCi/1 H-3 (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 (a) (a) Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) Water, Surface Gross (a) 19. pCi/l H-3 (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 (a) (a) Zn-54 (a) (a) Mn-5 4 (a) (a) I-131 (a) (a) Water, Precipitation Gross (a) 13. pC1/1 H-? (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 (a) (a) Zn-65 (a) (a) Mn-54 (a) (a) 1-141 (a) (a) 4-20
.- c TABLE 4-2-4
SUMMARY
OF PREOPERATION ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 (Cont'd.) Preoperational Concentrations _ Environmental Media Nuclide Median Value 95 Percentile Value Sea Water H-3 71. pCi/1 (b) Ba-140 2. pCi/kg 10. pC1/kg Cs-137 2. pC!/kg 10. pCi/kg Zn 1. pCi/kg 7. pCi/kg Mn-54 (a) (a) 1-131 (a) (a) K-40 200. pCi/kg 257. pCi/kg Ra-226 155. pCi/kg 544. pCi/kg Th-232 2. pCi/kg 7. pCi/kg Zr-9 5 (a) (a) Ru-106 (a) (a) Ce-144 2. pCi/kg (b) Air Gross (a) (a) Ba-140 0.004 pC1/m 3 0.016 pCi/m 3 Cs-137 0.002 pCi/m 3 0.013 pCi/m 3 4n-65 (a) (a) Mn-54 (a) (a) I-131 0.001 pCi/m 0.004 pCi/m K-40 (a) (a) Ra-226 0.048 pCi/m 3 0.261 pCi/m 3 Th-232 0.001 pCi/m 3 0.005 pC1/m 3 Zr-95 0.013 pCi/m 3 0.056 pCi/m 3 Ru-106 0.078 pCi/m 3 0.250 pCi/m 3 Ce-144 0.003 pCi/m 3 0.172 pCi/m 3 Milk Sr-90 4. pCi/l 6. pC1/1 Cs-134 (a) (a) I-131 (a) (a) Ba-140 (a) (a) Co-5 8 (a) (a) Co-60 (a) (a) Mn-54 (a) (a) l Zr-95 (a) (a) 4-21 l l
)
TABLE 4.2-4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 (Cont'd.) Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Oyster Meat Ba-140 3. pC1/kg (b) Cs -137 1. nCi/kg (b) Zn-65 5 >Ci/kg 33. pCi/kg Mn-54 pC1/kg (b) I-131 (a) (a) K-40 523. pCi/kg 1826. pCi/kg Ra-226 257. pCi/kg 534. pCi/kg Th-232 9. pCi/kg (b) '. Zr-95 1. pCi/kg (b) Ru-106 33. pCi/kg 82. pCi/kg Ce-144 9. pCi/kg (b) Blue Crab Ba-140 12. pCi/kg 55. pCi/kg Cs-137 17. pC1/kg 75. pCi/kg Zn-65 24. pCi/kg 127. pCi/kg Mn-54 3. pCi/kg 24. pCi/kg I-131 2. pC1/kg (b) K-40 1370. pCi/kg (b) Ra-226 1683. pCi/kg 3000. pCi/kg Th-232 17. pCi/kg 75 pCi/kg Zr-95 2. pC1/kg 13. - pCi/kg Ru-106 5. pCi/kg (b) Ce-144 43. pCi/kg 246. pCi/kg Mullet Ba-140 6. pct /kg 41. pCi/kg Cs-137 18. pCi/kg 55. pCi/kg Zn-65 16. pCi/kg 75.pCi/kg Mn-54 1. pCi/kg - (b) I-131 (a) (a) K-40 1926. pC1/kg 2739. pCi/kg Ra-226 1051. pCi/kg 2400. pCi/kg Th-232 60. pCi/kg 170. pCi/kg Zr-95 3. pCi/kg 12. pCi/kg Ru-106 17. pCi/kg 68. pCi/kg Ce-144 37. pCi/kg 240. pCi/kg 4-21a
TABLE 4.2-4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 (Cont'd.) Environmental Media Nuclide Median Value 95 Percentile Value
- Drums Ba-140 19. pCi/kg 100. pCi/kg (Scirenidae) Cs-137 37. pCi/kg 190. pCi/kg Zn-65 24. pCi/kg 168. pCi/kg Mn-54 4. pCi/kg 25. pCi/kg I-131 5.pCi/kg (b)
K-40 2191. pCi/kg 3569. pCi/kg Ra-226 1450. pCi/kg 7500. pCi/kg Th-232 7. pCi/kg 43. pCi/kg Zr-95 1. pCi/kg (b) Ru-106 23. pCi/kg (b) Ce- 144 7. pCi/kg (b) Terrestrial Fauna Ba-140 2. pCi/kg 12. pCi/kg C's -137 1912. pCi/kg 6500. pCi/kg Zn-65 11. pC1/kg 43. pCi/kg Mn-54 1. pCi/kg (b) 1-131 3. pCi/kg 16. pCi/kg K-40 1635. pCi/kg 2988.pCi/kg Ra-226 936. pCi/kg 4100. pCi/kg Th-232 14. pCi/kg 69. pCi/kg Zr-95 3. pCi/kg 12. pCi/kg Ru-106 45. pCi/kg 200. pCi/kg Ce-144 16. pCi/kg (b) ~ Food Crops Gross 2850 pC1/1 2900. pCi/l (Oranges) Co-5 8 . (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Sr-9 0 105. pC1/1 130. pCi/1 Cs-134 (a) (a) Cs-137 (a) (a) Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) 4-21b l l l l
s TABLE 4.2-4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 (Cont'd.) Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Vegetation Co-58 (a) (a) (Palmetto) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 145. pCi/1 3700. pC1/1 Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) Sargassum Algae Ba-140 2. pCi/kg 12. pCi/kg Cs-137 42. pCi/kg 86. pCi/kg Zn-65 62. pCi/kg 167. pCi/kg Mn-54 12. pCi/kg 50. pC1/kg I-131 16. pCi/kg (b) K-40 3295. pCi/kg 5727. pCi/kg Ra-226 557. pCi/kg (b) Th-232 116. pCi/kg 286. pCi/kg Ru-106 31. pCi/kg 150. pCi/kg Ce-144 17. pCi/kg (b) External Radiation All 62. rem /yr (b) Ocean Sediment Ba-140 1. pC1/kg (b) Cs-137 33. pCi/kg 180. pCi/kg Zn-65 (a) (a) Mn-54 2. pCi/kg 9. pCi/kg I-131 4. pCi/kg 28. pCi/kg K-40 398. pCi/kg 996. pCi/kg Ra-226 3357. pCi/kg 7100. pCi/kg Th-232 118. pCi/kg 197. pCi/kg
, Ru-106 261. pCi/kg 470, pCi/kg Ce-144 646. pCi/kg 1200. pCi/kg l
4-21c 1
TABLE 4.2-4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1973 (Cont'd.) (a) The median value is less than the minimum detectable value; no median value is given. (b) No value is available at this time. (c) In some cases the values listed are smaller than the minimum detectable value. Note: Prior to reactor startup, median values will be provided for the radionuclides for each environmental media classification listed on Table 4.2-5 or values of zero will be assumed.
)
l 4-21d
. /-
-r - -, - ,- - ,
aww - - Table 4.2-5 presents design object values pertaining to environmental media concentrations. The criteria for these values are limits in dose rate in unrestricted areas due to Crystal River Unit 3 operation; specifically the design objective limiting incremental increase in dose rate from radionuclides except I-131 is 5 mrem /yr and the design object-ive limit for dose rate due to I-131 from the plant is 15 mrem /yr. Most of the values listed in I'able 4.2-5 were derived from values in
" Environmental Radioactivity Surveillance Guide," ORP/SID 72-2, USEPA June 1972, pp.10,11 or in USAEC Regulatory Guide 1.42. The lists of nuclides considered for determination in air and in water are similar to the lists in USAEC Regulatory Guide 1.21 of nuclides to be determined in effluent streams. The design objectives of the Crystal River Unit 3 plant insofar as environmental media concentrations are concerned are that the radioactivity concentrations in the environment in the vicinity of the Crystal River plant, assuming that radioactivity from sources other than the Crystal River plant are insignificant, should not exceed, over e !
long term, values greater than the preoperational baseline median con-centration values on Table 4.2-4 plus the design objective limits of concentration increase values of Table 4.2-5. The operational surveillance program shall consist of: (1) a continuation of the program of measurements of radioactivity in environmental media which is outlined in Table 4.2-1, (2) reporting all the results of this program on a routine basis as described in Section 5.6.1 and (3) reporting the reaults of measurements of radioactivity in critical pathway 4-22
- w ,:-- TABLE 4.2-5 DESIGN OBJECTIVE LIMITS OF CONCENTRATION INCREASE Design Objective Environmental. Limit of Concentration Media Nuclide - Increases Water . H-3 5. nCi/l Co-58 610. pCi/l Co-60 3 3 0. pCi/1 Ba/La-140 122. pCi/l Sr-89 18. pC1/1 Sr-90 1.9 pCi/l Cs-134 167. pCi/1 Cs-137 357. pC1/1 Zn-65 1900. pCi/l Mn-54 610. pCi/l I-131 5.6 pCi/l Cr-51 12200. pCi/1 Air Particulates Sr-89 1. pCi/m Sr-90 0.1 pCi/Im 3 Cs-134 10. pCi/m Cs-137 20. pCi/m Ba/La-140 13. pCi/m Air Gases I-131 0.6 pCi/m Milk Sr-89 21. pCi/l Sr-90 2.2 pCi/l Cs-134 200 pCi/l Cs-137 455 pC1/1 I-131 2.3 pCi/l Edible Aquatic and Co-58 15. pCi/g Terrestrial Wildlife Co-60 7.4 pCi/g Cs-134 4. pCi/g 4-23
.x,:a =.- - . . .
TABLE 4.2-5 DESIGN OBJECTIVE LIMITS OF CONCENTRATION INCREASE (Cont'd .) Design Objective Environmental Limit of Concentr;. tion Media - Nuclide Increases Edible Aquatic and Cs-137 8.7 pCi/g Terrestrial Wildlife Zn-65 44.pCi/g (Cont'd.) Mn-54 15. pCi/g Sr-89 0.G pCi/g ' Sr-90 0.045 pCi/g I-131 0.046 pCi/g
' Vegetables and Cs-134 9.1 pCi/g Fruit Cs-137 20.pCi/g Sr-89 0.99 pCi/g Sr-90 0.10 pCi/g I-131 0.11 pCi/g External Gamma All 5% of background Radiation 4-24
[ environmental media samples on the non-routine bases described in Section 5.S.2. The critical pathway environmental media are air, potable water, milk and external gamma radiation. Detailed specifications per-taining to each of the environmental media are described in Sections which follow. 4.2.1 Potable Water Objective
- The objective is to monitor radioactivity in potable water in the vicinity of the plant to acquire and report information which may assist in the assessment of the radiation dose to man from water ingestion in unrestrict-ed areas due to plant operation.
Specification Samples of potable water, will be taken from locations and at frequencies listed in Table 4.2-1, and will be . analyzed according to the routine listed in Table 4.2-1 using procedures which will provide concentration values with minimum detectable limits which are equal to or less than those listed on Table 4.2-3. Reportino Requirement A. Individual potable water sample determinations which indicate radio-active nuclide' concentrations greater than the median preoperational con-centrations listed in Table 4.2-4 plus eight-times the design objective 4-25
,, .~
limits of concentration increase shown in Table 4.2-5 will be reported in accordance with specification 5.6.2.B.(1) . B. If the mean of the values of any radioactive nuclide concentration in potable water samples measured during a calendar quarter exceeds the median preoperational concentration listed in Table 4.2-4 plus twice the design objective limits of concentration increase shown in Table 4.2-5, results will be reported in accordance with specification 5.6.2.B.(2). C. Tb results will be reported in routine reports in accordance with Section 5.6.1. Bases The basis of the specification is that radioactivity concentrations will be determined by direct analysis of potable water samples. The basis of the reporting requirement is that concentration values which may be signifi-
. cantly above the design objective values will be reported non-routinely; all results will be reported routinely. -
4.2.2 Air Objective The objective is to monitor radioactivity in air in the vicinity of the plant to acquire and report information which may assist in the assessment of the radiation dose to man from inhalation of air in unrestricted areas due to the plant operation. 4-26 l
Specification Airborne particulate and gaseous iodine samples will be collected from locations and at frequencies listed in Table 4.2-1, and will be analyzed according to the routine listed in Table 4.2-1 using procedures which will provide concentration values with minimum detectable limits which are equal to or less than those listed on Table 4.2-3. Reportina Requirement A. Individual air particulate and gaseous iodine sample determinations which indicate radioactive nuclide concentrations greater than the median preoperational concentrations listed in Table 4.2-4 plus eight-times the design objective limits of concentration increase shown in Table 4.2-5 will be reported in accordance with specification 5.6.2.B.(1) . B. If the mean of the values of any radionuclide concentration in air measured during a calendar quarter exceeds the median preoperational concentration listed in Table 4.2-4 plus twice the design objective limits of concentration increase shown in Table 4.2-5 then the results will be reported in accordance with specification 5.6.2.B.(2) . C. The results will be reported in routine reports in accordance with Section 5. 6.1. i Bases i 1 The basis of the specification is that radioactivity concentration will be determined by direct analysis of samples of air. The basis of the reporting 4-27
requirement is that concentration values which may be significantly above the design objective value will be reported non-routinely; all results will be reported routinely. 4.2.3 Milk i. Objective The objective is to monitor radioactive nuclide corcentrations in milk produced in the vicinity of the plant to acquire and report information which may assist in the assessment of the radiation dose to man from ingestion of milk due to plant operation. Specification Samples of milk will be taken from locations and at frequencies listed in Table 4.2-1 and will be analyzed according to the routine listed in Table 4.2-1 using procedures which will provide concentration values with minimum detectable limits which are equal to or less than those listed on Table 4.2-3. Reporting Requirement A. Individual milk sample determinations which indicate radioactive
-nuclide concentrations greater than the median preoperational concentra-tions listed in Table 4.2-4 plus eight-times the design objective limits of concentration increase shown in Table 4.2-5 will be reported in accordance with Specification 5.6.2.B.(1) .
4-28
B. If the mean of the values of any radioactive nuclide concentration in milk measured during a calendar quarter exceeds the median pre-operational concentration listed in Table 4.2-4 plus twice the design objective limits of concentration increase shown in Table 4.2-5 then the results will be reported in accordance with Specification 5.6.2.B.(2). C. The results will be reported in routine reports in accordance with Section 5. 6.1. Bases The basis of the specification is that radioactivity concentrations will be determined by direct analysis of samples of milk. The basis of the report-ing requirement is that concentration values which may be significantly above the design objective values will be reported non-routinely; all results will be reported routinely. 4.2.4 External Radiation Objective The objective is to monitor the external radiation in the vicinity of the plant to acquire and report information which may assist in the assess-ment of the ambient radiation dose to man in unrestricted areas due to plant operation. l l 1 4-29 l 1 i I l
Specification Ambient external radiation levels will be measured at locations and frequencies listed in Table 4.2-1 using procedures which will provide radiation level values with minimum detectable increases over pre-operational mean background which are equal to or less than that listed in Table 4.2-3. Reportina Requirement The results will be reported in routine reports in accordance with Section 5.6.1. Bases The basis of the specification is that external gamma radiation in the vicinity of the plant will be measured directly. The basis of the report-ing requirement is that the results will be reported semi-annually (on the routine basis) and values which may be significantly above the design objective value will be noted and discussed. 4.2.5 Other Environmental Media Objective The objective is to monitor radioactive nuclide concentrations in various environmental media samples from locations in the vicinity of the plant, to acquire and report information which may assist in the assessment of concentrations in the environment due to plant operation. 4-30 .
Specification Samples of sea water, ground water, river water, bottom sediment, aquatic plants, aquatic animals, '.ood crops, vegetation, and terrestrial wildlife will be taken at locations and frequencies listed in Tad 3 4.2-1 and will be an:alyzed according to the routine listed in Table 4.2-1 using procedures which will provide concentration values with minimum detectable concentrations which are equal to or less than those listed on Table 4.2-3. Reportino Requirement The results will be reported in routine reports in accordance with Section 5.6.1. Bases The environmental media, the sampling locations, the sampling frequency and the analytical detection limits were chosen to provide information which may assist in the assessment of any long-term changes in environ-mental concentrations of radioactivity which are of a magnitude that could cause a radiation dose to man in the range of 5 mrem /yr. 4 4-31
* ^ ^
5.0 ADMINISTRATIVE CONTROLS Objective To define the organization, assign responsibilities, describe the environ-mental surveillance procedures, provide for a review and audit function, and prescribe the reporting requirements in order to insure continuing
. prot ec tion of the environment and implement the Environmental Technical Specifications .
S.1 ORGANIZATION The organization responsible for environmental protection, environmental monitoring and the implementation of the Environmental Technical Speci-fications, both prior to and following the issuance of an operating license for Crystal River Unit 3, is shown on Figure 5.1-1. 5.2 RESPONSIBILITY t The responsibility for the conduct of the preoperational environmental monitoring program described in Section 4 and special studies described in Section 6 is that of the Generation Engineering Department under the direction of the Director of Generation and Regulatory Affairs. Upon the issuance of an operating license the responsibility for the conduct of the postoperational environmental monitoring program and the imple-mentation of Environmental Technical Specifications becomes the re-sponsibility of the System Operations Department. 5-1
SENIOR VICE PRESIDENT SYSTEM ENGINEERING & OPERATIONS POSTOPERATIONAL PREOPERATIONAL
' ~
I l ASSISTANT VICE PRESIDENT ASSISTANT VICE PRESIDENT SYSTEM OPERATIONS GENERATION ENGINEERING I I DIRECTOR PRODUCTION GENERATION ENVIROMENTAL PERINTENDENT & REGULATORY AFFAIRS l l PRODUCTION GENERAL ENVIRONMENTAL STAFF PLANT SUPERINTENDENT I NUCLEAR PLANT SUPERINTENDENT I PLANT STAFF Figure 5.1-1 Organization fCr Implementing Environmental Technical Specifications 5-2 van 9 -e
The plant organization is responsible for the development of Operating and Surveillance Proccares oescribed generally in Section 5.5 and supplyira field data to the Produ: tion Environmental Staff as required by Sections 2, 4 and 6 of the Environmental Technical Specifications. The Production Environmental Staff is responsible for consultant contracts, state and local regulatory agreements, assembly of data preparation of reports required by Section 5.6 of these Environmental Technical Speci-fications, and making recommendations to improve environmental pro-tection practices. All reports and correspondence with the AEC regarding the Environmental Technical Specifications will be ap; roved and signed by the Assistant Vice President, System Operations. The Nuclear Plant Superintendent will, however, make reports by telephone and telegraph of any incident or occurrence requiring reporting within 24 hours or less, as required in Section 5.6. P 5.3 REVIEW AND AUDIT The FPC corporate Qualtiy Assurance organization under the direction of the Director of Quality and Standards has the responsibility of auditing the adequauy of the environmental monitoring and surveillance programs and auditing conformance to procedures and Environmental Technical Specification requirements. Figure 5.3-1 shows the reporting path for the Director of Quality and Standards that is independent of the System Operations Department. 5-3 1
~ . . . The Nuclear General Review Committee also has a reporting path inde-pendent of the System Operations Department as shown on Figure 5.3-1. This Committee will normally fulfill its responsibilities by conducting reviews and reporting the results of these reviews to the Senior Vice President, System Engineering and Operations. However, in accordance with the Nuclear General Review Committee Charter, the Nuclear General Review Committee has the authority to conduct audits of any portion of the Production Department's Quality Control Program. The Nuclear General Review Committee functions as they relate to the Environmental Technical Specifications are as follows: A. Review the results of the environmental monitoring program prior to their submittal to the AEC in each Semiannual Station Environmental Report. See Section 5.6.1. B. Review and make recommendations on proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes. C. Review proposed changes or modifications to plant systems or equipment and the evaluated impact which would require a change in the procedures described in (D) below or which would affect the evaluation 1 of the plant's environmental impact as described in Section 5.4.2.(B). D. Review sampling, analysis, calibration and alarm check procedures, as specified in Section 5.5.1, and any other procedures or changes thereto as determined by the Nuclear Plant Superintendent to affect the plant's environmental impact. 5-4
SENIOR VICE PRESIDENT SYSTEM ENGINEERING & OPERATIONS p-- ________- ASSISTANT VICE PRESIDENT ASSISTANT VICE PRESIDENT GENERATION ENGINEERING SYSTEM OPERATIONS DEPARTMENTS t > f PRODUCTION DIRECTOR SUPERINTENDENT OUALITY & STANDARDS NUCLEAR GENERAL REVIEW COMMITTEE l PLANT REVIEW COMMITTEE LEGEND:
--- OUALITY ASSURANCE REPORTING MANAGEMENT RESPONSIBILITY Figure 5.3-1 Organization for independent Review and Audit 5-5
E. Review reported instances of violations of Environmental Technical Specifications and abnormal environmental occurrences. Where investi-gation indicates, evaluate and formulate recommendations to prevent recurrence. F. Review and compare the Safety Technical Specifications and the Environmental Technical Specifications to avoid conflicts and maintain consistency. 5.4 ACTION TO BE TAKEN IF AN ENVIRONMENTAL PROTECTION CONDITION IS EXCEEDED 5.4.1 Remedial actions as described in Section 2.0 of these technical specifications will be implemented until such time as the environmental protection condition is met. 5.4.2 The occurence shall be promptly reported to the Chairman of the Nuclear General Review Committee and investigated as specified in Section 5.3. 5.4.3 The Nuclear General Review Committee shall prepare and submit promptly a report in writing to the Assistant Vice President, System Operations . The report shall describe the circumstances leading to and resulting from the occurrence, and shall recommend appropriate action to prevent or reduce the probability of repetition. 5.4.4 The Assistant Vice President, System Operations , shall transmit a report of the occurrence to the AEC as specified in Section 5.6.2. 5-6
.ad--
, . 5.5 PROCEDURES i 5.5.1. Detailed written procedures, including applicable check-off lists and instructions, shall be prepared for the implementation of the monitoring requirements described in Sections 2 and 4, approved as specified in Section 5.5.2, and adhered to for operation of all systems i and components involved in carrying out the effluent release and environmental monitoring programs. Procedures shall include sampling, instrument calibration, analysis, and action to be taken when limits are approached or exceeded. Calibration frequencies and standards for instruments used in performing the measurements shall be included. Testing frequency of alarms shall be included. These frequencies shall
~
be determined from experience with similar instruments in similar environments and from manufacturers' technii al manuals. t 5.5.2 All procedures descri 'n Secd>>n 5.5.1 above, and changes thereto, shall be reviewed as specified in Section 5.3 and approved by j the Nuclear Plant Superintendent prior to implemenotion. Temporary I changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by two =em-bers of the plant management staff, one of whom holds a senior operator's license.- Such changes shall be documented, subsequently reviewed and 2 approved by the Plant and Nuclear General Review Committees. 5.5.3 Prior to special tests or changes: A. If the Nuclear Plant Superintendent decides to make a change in the facility or Operating Procedures, or to conduct a test or experiment, and concludes that the proposed change, test, or experiment does not involve 4 5-7
~ _
a change in the Environmental Technical Specifications or an unreviewed environmental question, he may order the change, test, or experiment to be made, shall enter a description thereof in the operating records of the facility, and shall send a copy of the instructions pertinent thereto to the Chairman of the Nuclear General Review Committee for review. B. If the Nuclear Plant Superintendent desires to make a change in the facility or Operating Procedures, or to coi .ct a test or experiment which in his opinion might involve a change in the Environmental Technical Specifications, or involve an unreviewed environmental impact question, he shall not order such change, test, er experiment until he has referred the matter to the Nuclear General Review Committee for review and report. If the Committee is of the opinion that the proposed change, test, or experiment does not require approval by the Atomic Energy Commission under the terms of said license, it shall so repot' in writing to the Nuclear Plant Superintendent, together with a state-ment of the reasons for the Committee decision and the Nuclear Plant Superintendent may then proceed with the chance, test, or expedment. If on the other hand the Committee is of the opinion that approval of the Atomic Energy Commission is required, the Committee shall prepare a re quest for such approval, including an appropriate environmental anal) lis in support of the request, and following Committee concurrence, forward its report to the fenior Vice President of System Engineering l and Operations for his review with a copy to the Nuclear Plant Super-intendent. I l 1 l l 5-8 1 l 1
5.6 PLANT REPORTING REOUIREMENTS 5.6.1 Routine Reports A semiannual Station Environmental Report covering the previous six months of operation shall be submitted to the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) within 60 days after January 1 and July 1 of each year. The first such period shall begin with the date of initial criticality and terminate on January 1 or July 1, depending on the date of initial criticality. These reports shall include the following: A. The environmental surveillance data. The radiological environ-mental surveillance data will by summarized on a quarterly basis follow-ing the format of Table 5.6-1. B. Analysis of the environmental surveillance data. This analysis will include discussion of any indications of radioactivity concentra-tions which are significantly higher than background levels. C. Rccords of changes in survey procedures. D. Records and results of Special Surveillance, Research, or Study Activities which are in progress or have been recently completed. E. Records of any occurrences in which an Enviromental Protection Condition was exceeded. 5-9
F. A summary of the quantities of radioactive effluents released from the p. ant as outlined in USAEC Regulatory Guide 1.21, with data summarize.d on a monthly basis following the format of Appendix " A" thereof. G. Records of changes as described in Section 5.6. 3. 5.6.2 Non-Routine Reports A. Radioactive Discharge If measured rates of release of radioactivity to the environment, averaged over a calendar quarter, exceed the design objective rates as specified in specifications 2.4.1 F for liquid effluents and in 2.4.2 G for air-borne effluents the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) will be notified within 30 days along with a report of the causes of the release rates and of a proposed pro-gram of action to reduce the release rates. B. Radiological Environmental Monitoring
- 1. If a single measured value of radic.n:tivity concentrations in critical pathway environmental medium samplai identified in Section 4.2 exceeds a value equal to the preoperational background value as defined in Section 4.2 plus eight-times the design objective maximum increase over background as defined in Section 4.2 then: (1) a study of other available data and of repeat analyses to confirm or deny the validity of the h4h value will be made and the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) will be 5-10
3 ( 4
~ notified within one week of verification, (2) the Director of the Regional USAEC llegulatory Operations Office (cc to Director of Licensing) will be
. notified of the results of the study within twe weeks of the completion i j . of the, study.
- 2. If the average of the values of radioactivity concentrations in
- .any critical pathway environmental media samples measured during a calendar quarter exceeds a value equal to the preoperational background value as defined in Section 4.2 plus twice the design objective maxi-mum increase over background as defined in Section 4.2 the Director of the Regional USAEC Regulatory Operations Office (cc to Director of f Licensing) will be notified within 30 days of
- (1) the measured values, (2) a study of other available data including plant discharge data to ascertain whether or not Crystal River Unit 3 operation is the source and Wi if th'e Crystal River Unit 3 operation is the source, of an appropriate plant of action.
C. Nonradiological Discharges and Environmental Monitoring
- 1. Ip the event that a limiting condition for operation is exceeded
{ or an event involving a significant adverse environment impact occurs, a report will be made within 24 hours by telephone and telegraph to the Director.of the Regional USAEC Regulatory Operations Office followed by a. written report within one week. The telegraph report will quantify 1-
. the occurrence, its causes and, .if aspects of the Crystal River Unit 3 operation are among the causes,. planned remedial action to the extent possible. The written report will fully describe the occurrence and will describe its causes and corrective action as fully as possible.
!/ 5-11
TABI.E 5.6-1 REPORTING OF RADIOACTIVITY IN THE ENVIRONS Factitty Docket No. Reporting Period A. Sa+ ele pesults Averaae Ouarterly Results Analysts Results Frequency andl/ (spectly radio-Sammte Location Tvoe of Sammles nuclide or entity) Remarks (1) External Radiation (2) Filterable Airborne
- a. Partic tlate Filters 1) 2)
etc.
- b. Charcoal Filters 1) 2)
etc. (3) Watery a. b. etc. (4) Food (Human) a. b. etc. (5) Other Media
- a. Vegetation (include pasture and other animal foodstuffs)
'b. Soils
- c. Sediments
- d. Fish
- e. etc.
Expialn any unusual measurements or deviation from sampling schedule. Use the following units: external radiation, mrem / quarter; filterable airborne, water and milk, pC1/ml; soll, pct /m 2 (specify depth), precipitation, pct /m 2; stream sediments and terrestrial and aquatic vegetation, pct / dry gm: other media, specify units. Specify location and its distance and direction from the facility, and indicate which is used for background. Indicate whether prectpttation, surface, ground, Lake, river, ocean, etc.: specify drinking water. Use separate table for each quarter. W Type of sample means either greb, continuous,. proportional, compostte, etc. 5-12
- 2. In the event that a reporting level specified in Section 4.1 is reached, a report will be made within 30 days to the Director of the Regional USAEC Regulatory Operations Office.
The report will describs- (1) efforts to confirm or deny the validity of the observation, (2) efforts to determine the causes and whether aspects of the Crystal River Unit 3 operation are among the causes and (3) planned action to prevent reoccurrences. 5.6.3 Changes A. When a change in a plant design feature or operating practice as described in Section 3.0 or a procedure described in Section 5.5 is planned which, in the judgement of the applicant, would have a signifi-cant adverse effect on the environment or which involves an environ-mental matter or question not previously reviewed and evaluated by the AEC, a report on the change will be made to the Deputy Director of Reactor Projects, Directorate of Licensing, USAEC (cc to Director of the Regional Regulatory Operations Office) prior to implementation. The report will include a description and evaluation of the change. B. Changes or additions to permits and certificates required by Federal, State, local or regional authorities for the protection of the environment will be reported. When the required change is submitted to the con-cerned agency for approval, it will also be submitted to the Deputy Director of Reactor Projects, Directorate of Licensing, USAEC (cc to Director of the Regicnal Regulatory Operations Office), for information. The submittal will include an evaluation of the environmental impact of the change. 5-13 i
C. Request for changes in environmental technical specifications will be submitted to the Deputy Director of Reactor Projects, Directorate of-Licensing, USAEC (cc to Director of the Regional Regulatory Operations Office), for prior review and authorization. The request will include a description and an evaluation of the proposed change. 5.7 RECORDS RETENTION 5.7.1 Records and logs relative to the following areas will be retained for the life of the plant: A. Records and drawing changes reflecting plant design modifications made to systems and equipment as described in Section 5.6.3. B. Records of environmental surveillance data. C. Records to demonstrate compliance with the limiting conditions for operation in Section 2.0. 5.7.2 All other records and logs relating to the environmental technical specifications shall be retained for five years. 5-14 t
~ 6. 0' SPECIAL SURVEILLANCE, RESEARCH, OR STUDY CTIVITIES -
6.1- SPECIAL PREOPERATIONAL ENVIRONMENTAL STUDY Introduction
- As a result of comments on the Draft Environmental Statement received from a number of government agencies, principally the Environmental Protection ~ Agency and the Department of the Interior, a series of meetings was held to develop a program aimed at determining the adequacy of the designed cooling system for Crystal River Unit 3.
In discharging its responsibilities under the FWPCA, the EPA is concerned
. with the discharges from all three Crystal River Units. The program described here attempts to incorporate as much as possible the elements i that will allow the EPA to exercise its regulatory responsibilities.
Problem A. To obtain necessary data of the Crystal River Site area from a
, . coordinated and comprehensive hydrological investigation.
- B .- To identify a. d quantify those factors that have impacted the
- Crystal River environment and to obtain necessary information on aquatic
- organisms and water chemistry in the Crystal River Site area in order to be able to assess the potential impact on the aquatic biota fron: the operation ofiUnit 3.
1 T
- : e y p ~ - , . , , - - - . -
Purpose To determine the adequacy of the proposed cooling system for Crystal River Unit 3. Objective To provide a basis for a decision with regard to the need for an alternative cooling system for Unit 3 no later than November,1974. General Discussion The AEC staff, in conjunction with other interested federal agencies, requires additional information in order to predict the incremental impact on the aquatic biota from the operation of Crystal River Unit 3. Of necessity this assessment must be based on data collected in conjunction with the operation of the oil-fired Units 1 and 2. The specific areas of concern are hydrology in the immediate plant environs; entrainment of organisms through the condensers; impingement of organisms on the intake structure; entrapment of aquatic organisms in the intake system; thermal, chemical and physical impact in the discharge area; and biota surveys in areas which may be affected by candidate alternatives to the proposed once-through cooling system. In conjunction with the study program required in each of these areas, the applicant will concurrently initiate and complete detailed hydrological-environmental assessments of alternative cooling systems to identify those systems which would impose the minimum environmental impact, taking into account the areas of concern expressed above, including terrestrial impacts which are not involved in the proposed once-through cooling system. 6-2
Specific Procrams A. Entrainment
- 1. Objectives
- a. To determine the sources of cooling water and their -
relative importance under normal hydrologic and meterological conditions and, to the extent possible, to determine variations from the normal pattern caused by abnormal tide, wind, or surface water runoff.
- b. Estimate power plant " predation" and its efficiency as a predator in zooplankton standing crop, production.and species diversity,
- c. Determine the effects of entrainment on the major species of copepods, focusing upon percent mortality, delayed lethal and sublethal effects.
- d. Estimate phytoplankton biomass, productivity and species diversity in both the discharge and intake areas as well as the surrounding er.virons.
- 2. Procedures for Source of Intake Water The sources of the cooling water will be investigated on a priority basis.
As the present research uncovers questions which must be addressed, thesa new areas will be researched. . The techniques outlined in
,6-3
Environmental Research Procrams at the Crvstal River Power Plant, A_ Technical Discussion will be used, supplemented as necessary. Abnormal conditions will be modelled and the model will be confirmed where possible.
- 3. Procedures for Plankton
- a. Length of program. Field sampling began in September, 1973, and will continue through October,1974.
- b. Sampling stations have been established in the areas indicated in Figure 6.1-1.
- c. Frequency of Sampling and Techniques These may be found in Florida Power Corporation Crystal River Environ-mental Research Procram to meet current Federal Requirements June 11, 1973, and its addendum entitled Proposed Plankton and Water Ouality Program at Crystal River.
B. Impingement /Entmpment i
- 1. Objective To quantify the numbers, size / age class, and weight of species impinged
- on the existing travelling screens and to investigate the mechanism (s) for controlling or determing screen impingement of the resident and entrapped )
canal ' fauna . l l l 6-4
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(i 0 J NAUTICAL MI' ".S 2 f l'II q M] j,' p, k g to Figure G.1-1 Sampling Station for the Special Preoperational Environmental Plankton Study
m.. .-
- 2. Procedure to Assess Impingement
- a. Length: A minimum of 12 consecutive months of data analyzed prior to November,1974.
- b. Sampling Stations: Samples will be collected at both screens to determine what statistical differences, if any, occur in the screen. The basic collecting will be at the western screen.
- c. Frequency of sampling and techniques: Subject to third-party statistical review, the procedures outlined in Environmental Research Programs at the Crystal River Plant, A Technical Discussion, ,
Florida Power Corporation, March,1973, will be implemented.
- 3. Intake Canal Organisms Study resident and migratory species, intake canal recruitment and time of arrival, population, characteristics, and behavior relative to time, tide, season, barge movements and intake velocities.
'4. Diversion Techniques Studies of means for returning impinged species to the Gulf or diverting organisms before they reach the intake structure will be conducted in conjunction with the entrapment and impingement study.
6-6
.w ,. ; __
- 5. Other E. The number of pumps in operation will be recorded and the approximate flow volume may be calculated from this.
- b. Screen flow and velocity will be correlated with impingement,
- c. Verticitl and lateral velocity, salinity, and temperature measurement will be taken at selected critical points in the intake canal.
These measurements, together with bottom profiles will be used to establish canal flow and velocity characteristics. C. General Survey
- 1. Objective
- a. To survey areas potentially subjected to impact from alternative cooling schemes.
- b. To survey areas of concern in assessing environmental impact which have not been previously investigated or documented.
- 2. Specific Studies
- a. Locate spawning and nursery areas and compile existing data on these areas.
6-7
,.; 3 .
- b. Inventory of terrestrial flora and fauna and estimate the population of important species,
- c. Obtain background levels of atmospheric salt content.
D. Thermal / Chemical Impacts in Discharge Area
- 1. Objective
- a. To define the existing three-dimensional thermal plume.
- b. To calibrate the thermal plume mathematical model to better simulate the existing and predicted plume under all modes of operation.
- c. Water chemistry - to obtain base line data.
- 2. Thermal / Chemical Effects on Biota
- a. The abundance and distribution of the major environmental compartments will be quantified to develop seasonal baseline data in the projected discharge area. Intensive sampling will be undertaken in the area bounded by the U. S. Atomic Energy Commission's predicted 8 F isotherm which is shown on Figure 6.1-2.
Reports and Procram Chances The results of this study will be reported via quarterly reports; changes in the program will be discussed in these reports. 6-8 l-
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. ... - X-- 6.2 THERMAL PLUME DURING UNIT 3 OPERATION Obj ective To establish the location and size of the thermal plume during operation, under conditions of high and low tide and maximum and minimum intake temperature; to provide data to verify the mathematical and physical models so that good predictions of isotherm location under all conditions will be possible and to establish the operational monitoring system. General Approach and Schedule Intensive field surveys shall be conducted twice during the first year of operation. Specifically, the surveys will be done during the m' ,ths of July or August when the maximum intake temperature is observed and during the months of December or January for contrast when the minimum intake temperature is observed. The thermal field measurements shall be made in sufficient locations to cover the full extent of the thermal plume . Salinity measurement may be required in order to effectively decouple the plume from ambient isotherms. During the tests the behavior of the plume during both phases of the tidal cycle will be tested. The measure-ments should allow for construction of the isothermal maps with 1.0 F above ambient contour intervals. These tests shall be carried out with all three Units operational and under at least 80 percent of full capacity. During the surveys the following conditions shall be recorded as needed to assess the extent of the thermal plume and its correspondence to a 6-10
~
?
computer run with parallel parameters: (a) plant conditions (condenser flows, intake temperature, discharge temperature, loading, etc.) of all three units, (b) hydrological conditions (tidal stage, salinity traverses, etc. , (c) meteorological conditions (wet and dry bulb temperature, humidity, wind speed, wind direction, solar radiation, etc.) . The field survey measurements will be compared to the results of the computer runs. Any modifications needed in either the physical model or the mathermatical model will then be incorporated in the models. The models will then be available to use in the evaluation of any abnormal environmental occurrence or other modifications in plant system or equipment performance. 6.3 INTAKE VELOCITY DETERMINATION Objective To measure the velocity of water at the intake screens and to verify the validity of the calculuted value of intake velocity. General Approach and Schedule
' The intake velocity will be determined with appropriate instrumentation with an accuracy of10.1 fpm during operation of all three units within a period of one year after startup of Unit 3.
l i l 6-11
6.4 STUDY OF EROSION IN THE DISCHARGE SYSTEM Objective To study scouring and deposition in the discharge system. General Approach and Schedule It is expected that doubling of the discharge volume flow rate by the addition of Unit 3 will nearly double discharge canal velocities and thus could increase the scouring already occurring in the canal. If the canal turbidities were doubled, they would be approximately the same as those of the Withlacoochee River Barge Canal Waters. Much of the scoured canal sediment would be deposited about a mile and a half down the canal and to the west where the currents diverge. Since the scoured discharge canal particules are expected to be larger in grain size than the sediments suspended in the slower Withlacoochee waters, near-canal regions would be affected by scoured canal suspended sediments. These particles would most likely be quickly redeposited once the canal currents slowed upon divergence. The contribution to the turbidity characteristics of the characteristics of the region will continue to be dominated by the suspended loads associated with the Withlacoochee Refer-Barge Canal complex. Sediment levels and particle size are being: investigated in areas of cormern and changes in the community structure can be detected. 4
- 6-12
- _.= -
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=
TABLE Ol' CONTENTS (Cont'd.)
. Page No.
1.5 ADMINISTRATIVE CONTROLS 1-6 1.6 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 1-7 [ I,%) Limirwr. coreomods roa cPsamTi(>4 2.0 E!!""'O!"'E!!T?.L "".OTECTIO!! CO!!O!T!O!!C 2-1 2.1 THERMAL 2-1 2.1.1 Maximum AT Across the Condenser 2-1 2.1.2 Maximum Discharge Temperature 2-2 2.1.3 Maximum Heat Rejection Rate 2-4 2.1.4 Rate of Chance of Discharge Temperature 2-4 2.1.5 Heat Treatment of Circulating Water System 2-4 2.1.6 Deicino Operation 2-4 ' 2.2 HYDRAULIC 2-5
. 2.2.1 Intake Velocity 2-5 i
2.2.2 Discharge Velocity 2-5 2.2.3 Plow Rate Restriction 2-5 2.2.4 Reservoir Drawdown 2-5 2.3 CHEMICAL 2-6 2.3.1 Biocides 2-6 2.3.2 Corrosion Inhibitors 2-8 2.3.3 Suspended and Dissolved Solids 2-8 2.3.4 pH 2-8 2.3.5 Otne. Chemicals Which Affect 1 l l_ Water Quality 2-8
! l l
l 'L . 11 l
-r TABLE OF CONTENTS (Cont'd.)
Page No. 4.1.1 Thermal Plume Model Verification 4-3 4.1.2 Benthos in Discharge Area 4-4 4.1.3 _ Marsh Grass 4-5 4.1.4 Impingement on Intake Screens 4-6 4.1.5 General Ecological Survey 4-8 4 . 2' RADIOLOGICAL ENVIRONMENTAL MONITORING 4-10 4.2.1 Media Other Than Milk, Green Leafy Vegetables or 4-31 External Ganna Radiation 4.2.2 Milk and Green Leafy Vegetables i~33
~
4.2.3 ExteNa1 Radiation 4-23 5.0 ADMINISTRATIVE CONTROLS 5-1 5.1 _ ORGANIZATION 5-1 5.2 RESPONSIBILITY 5-1 a 5.3 REVIEW AND AUDIT . _ _ _ _ . . _ , 5-3 5.4
- ,) _ ACTION TO BE TAKEN IF A Alpineer. CpDiM ,.
FOR OPERA 78 ort 15 EXCEEDED 5 -6 5.5 PROCEDURES 5-7 5.6 PLANT REPORTING REOUIREMENTS 5-9 1 i 5.6.1 Routine Reports 5-9 5.6.2 Nonroutine Reports 5-10 5.6.3 Changes 5-13 5.7 RECORDS RETENTION 5-14 6.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 6-1 l w iv 1
9 y
- LIST OF TABLES No. Page No.
2.4-1 RADI0 ACTIVE LIQUID WASTE 2-12 SAMPLING AND ANALYSIS SCHEDULE 2.4-2 RADI0 ACTIVE GASE0US WASTE 2-18 SAMPLING AND ANALYSIS SCHEDULE 3.3-1 CHEMICAL USAGE 3-5 4.2-1 GENERAL PATHWAY RADIOLOGICAL ENVIRONMENTAL 9-lg
- MONITORING PROGRAM 4.2-2 CRITICAL PATHWAY RADIOLOGICAL ENVIRONMENTAL #f- 19 MONITORING PROGRAM.
4.2-3 SAMPLE STATICN LOCATIONS 4-2D 4.2-4 TYPICAL MINIMUM DETECTABLE CONCENTRATIONS 9- 2,l 4,2-5 SUMARY OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1974 i-23 4.2-6 MAXIMUM CONCENTRATION INCREASES FOR DESIGN RELEASES ef_3 f 5.6-1 REPORTING OF RADI0 ACTIVITY IN THE ENVIRONS S-/2. l l
f 1.0 DEFINITIONS The following terms are. defined for uniform interpretation of the Environ-mental Technical Specifications for Crystal River Unit 3. 1.1 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (ETS)' Refers to;all of the information concerning any limitations, conditions and requirements imposed on the applicant which are considered necessary for the protection of the environment. There are 5 types of ETS: (1) Lid:Es
~
( l,%) Cowsinws ne 'OrunEod , (2) Design Features and Operating Practices, (3) Environmental Surveillance, (4) Administrative Controls and (5) Special Surveillance, Research, or Study Activities. LIMrfidr. C.orJDiTsDds foR ov'sAA1104 1.2 EN'/IECN!4 ENTAL "ROTECTION CONO!TIONE Limiting conditions imposed on plant effluents which may have an adverse impact on the environment, which are specified in Section 2.0 and which consist of an objective, specification, monitoring requirement and bases. 1.2.1 Objective The plant effluent parameter or operating practice which is to be limited
, including an identification of the system and location to which the limit pertains and the purpose (s) of the limiting condition including t% pecific potential adverse environmental impact (s) which the limiting condition is intended to avoid or limit.
em 1-1
- r
( 1.2.2 Specification
=
A quantitative limiting yalue of a plant effluent parameter or a specific operating practice requirement intended to limit on adverse environmental impact. In the case of radioactive liquid and airborne offluents, specifica-tions of offluent c oncentrations above which a report is required, arc included. 1.2.3 Monitoring Requirement (fjW,) A description o; the observations which will be made to provide the informa-
, tion to show compliance with anLini Er .rn C.aogo,* toe p,ermerta. On=apo,4
rct_, tier _ ditier. This description will normally include general descriptions of the measurement
- methods, sampling methods, location of the measurement, sampling or measurement frequency, accuracy, sensitivity and record keeping. Terms
, used to specify frequency are defined as follows:
i (2) Once per shift - three times per day, interval may vary 92- -' 1: 12 hours. Daily - Not less than 360 times per year, interval may vary by att
,,, 4 hours.
Weekly - Not less than 48 times per year, interval may vary by _ 13 days.
, Monthly -
Not less than 10 times per year, interval may vary by
, 115 days.
Quarterly 1 Not less than 4 times per year, interval may vary by 30 days. Semi-annually - Not less than 2 times per year, interval may vary i.'y _t 60 days .
.. s 1-2
4 1.2.4 Bases The considerations in developing the specification and monitoring require-
, ment from the objective of limiting a potentially adverse environmental impact. Normally these considerations will include the reasons for the ,, limitation in terms of an environmental impact and consideration of pertinent design capabilities of the system and of special system require- , ments . .
I.2.5. GROSS @,v) ANALYSIS [g6). __ Refers to radioactivity measurements of gross beta or gross beta. in conjunction with gross gansna as defined in Regulatory Guide 1.21. 1.2.6 Point of Discharge (POD) o = The original bulkhead line which can be recognized on maps of the site as approximately the line of the existi'ig outer dike between the intake and _ (47) discharge canals as siwa.= o re F ysc 3.7.1, p. 3-sz . , 1.2.7 AT Across the Condenser Rc'a.s to the average t mperature difference between the inlet and outlet of Unit 3 condenser boxes. 1.2.8- Unit 3 Mixino Zone ~ Refers to the enclosed area of the discharge canal bounded by the eastern end of the canal and the cable chase from Units 1 and 2 crossing the canal. 1-3
b 1.2.9 Emergency Need for Power Refers to a regional electric power shortage such that if - electrical generation of Crystal River #3 was reduced or was not available, temination of service would be imperative. 3 1.3 DESIGN FEATURES AND OPERATING PRACTICES A description of the design, operation, maintenance and/or management of plant systems including the site and transmission corridors, modifica-tion of which could result in a significant change in environmental impact (s) . 1.4 ENVIRONMENTAL SURVEILLANCE A program of sampling, analysis and reporting with the purpose of detecting impact (s) due to plant operation and which is described in Section 4.0. The program is designed to obtain information to assist in detecting impacts to the ecosystem, in many cases by comparison to measurements following plant start-up with those made prior to plant start-up. A ' program element
~
certains to each environmental parameter which is measured and consists of an objective, specification, reporting requirement and bases. 1.4.1 Objective The'enyironmental parameter which will be measured and the purpose, !
~
1 within the context of the whole program, of the measurement. I [i)
~
~ l'.530 'KNOWN RADI0 ACTIVE SOURCE
~~ ~~
- l Refers to a referenced calibration source capable of reproducible l geometry. The source and geometry shall be referenced to the original
_ _ _ _ _ monitor _ calibration which produced the applicable calibration curves. g 1.2.11 ABNORMAL POWER OPERATION
~ ~ ~ ~ ~
~
~~
Refers to the operation of Crystal River Unit 3 beyond these technical
' specifications due to the Emergency Need For Power.
I-9 1
~
f' 1.4.2 Specification Environmental sample description, sampling locations and frequency, measurements to be made on the samples, and measurement quality criteria such as accuracy or minimum detectable concentration. Terms used to specify normal sampling frequency have been defined in Section 1.2.3, In unusual circumstances, for example during hazardous weather conditions, the sampling interval may be al'tered. The reasons for such alterations will be reported in the next routine report. 1.4.3 Reportino Requirement The requirement to report the results of the environmental surveillance program in terms of time and in terms of environmental parameter values. 1.4.4 Bases $ The considerations in developing the specification and reporting require - ment from the objective. These considerations may include pertinent criteria of environmental impact including the normal fluctuations of the value of the environmental parameter in terms of both time and place and ,, the importance to man and/or the ecosys' tem of the impact. 1.4.5 Intake Area
, The intake canal and all of the water area south of the north intake dike NLES and within two hu:Netre of the west tip of the south intake dike.
9 .
-k 1-5
. -s 4
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~
1.4.6 Discharon Area The discharge canal and all of the water area north of the south discharge dike anti within two miles of the west tip of the north discharge dike. 1.4.7 Inner Bay Five feet or less in depth composed of a mixture of grassy bottoms, oyster associations, algal bottoms and areas of sand and mud.( SEF- by'tG !.N.7 ) 1.4.8 Outer Bay The outer basin in which the planktonic ecosystem becomes as important as the bottom ecosystems. (see F,30(e I.4.7) a 1.5 ADMINISTRATIVE CONTROLS The assignment of responsibilities, organizational structure, review and audit functions and procedures. These administrative controls specify: ( ;e 4O um rot. omtaTioA (1) action to be taken if an er"y as c *oare,+_rcrmcrt:1 prctccucn ccnincn is exceeded, (2) sampling methods, analytical techniques, etc. to carry out the j environmental technical specifications, (3) assurances that plant operating i u procedures will be in compliance with the ea'*"'T'd' ' * * '
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(/j'16) (4) reporting schedules, (5) the mechanisms for changes in design features I and operating practices, in permits, etc. , and in the environmental technical specifications and (6) records retention. l s 1-G eI
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s 4 g 2.0 CNVIRONMENTAL PROTECTION CONDITIONS , 2.1 THERMAL , Obj ective To define the conditions for discharge of the effluent cooling water at the point of discharge to assure compliance with applicable Federal and State regulations to limit thermal stress to the aquatic ecosystem and minimize adverse thermal effects of Crystal River Unit 3 on marine biota. 2.1.1 Maximum AT Across Condensers Obj ective
, To limit the maximum temperature rise across the condenser ' during normal operation at all power levels.
o Specification
. , __= . _ . . _ _ _ _ _ _ _
(Sj llj A. If the temperature rise across the condenser is greater than 17.5'F "3 for more than 3 hours thereby exceeding this Limiting Condition for i Operation, corrective action shall be taken to reduce the AT to within the specified limit.
. 2-1 b
e
- m. _ _ _
,m (5,21) B. During power operation, when the temperature rise exceeds a maximum of 210F
( insnediate action shall be taken to reduce the rise to less than 21 F. (6) C. During an emergency need for power, the maximum temperature rise across the condenser shall not exceed 24 F for more than 1 hour before corrective action shall be taken to reduce the AT to less than 24 F. - (5,22) Monitoring Requirement A. The condenser temperature rise shall be monitored by detectors (RTD's 0-200 o il F), from which the signal will be comaw . to the control room. computer. B. The AT will be alarmed at 17.5 F for normal operation and for 3 hours of operation above 17.5 F. C. The AT will be alarmed at 21 F for a maximum during normal operation. D. The AT will be alarmed at 24"F for a maximum during an emergency need for power. l 1 l 4-1 A s
[ w;~ (RTO';) (0 200.. I "), t.m sign:! fr r- ^ g E. th; ;: :::: :::r : =;_t:r. ouring power operations . . the RTo s or
> *M 4 hoeu 8 computer are inoperative, the condenser AT shall be determined c(r=e:t per
,
- M utilizing local temperature indicators on each water box (30-130 2 F).
Bases 5Hom.o When Unit 3 is operated at design capacity, the intake temperature w444-be elevated by a dee, syn value AT of 17.5 F. When any one shell of the
. two twins shelled surface steam condensers are inoperative for maintenance or other reasons , the AT will m.C w rise.aeeedi .;;; Each of the 4 =
condenser sections will require cleaning every 4 weeks, due to the buildup of marine growth or debris in the pipes and condensers. During extreme climatic conditions , especially during tropical storms, sea grass is up-rooted from the Gulf of Mexico, requiring temporary shutdown of a circula-. tor to clean grass and other debrie which has accumulated at the intake structure or inside the condenser water boxes. This will cause a tempore w increase in the AT across the condenser. Because of these conditions the AT of 24 F for a period in excess of k hourg is specified as a limit. Monitoring by means of RTD's in the condenser inlet and outlet water boxes will provide reliable values of the AT across the condenser. 2.1.2 Maximum Discharge Temperature Objective To limit the maximum temperature of the water discharged from the plant to the environment.
'~
7-2 L
( Specification
. 23 A. The temperature at the POD shall not' exceed 103 F for a period of 3 hours,Whenever 24) the temperature is above 103'F for a period greater than 3 hours, corrective action shall be taken to the extent necessary to maintain 103 F at the POD unless there is an emergency need for power.
s . (49) B. If the temperature exceeds lu60 F at the POD, imediate action shall be taken to comply with A.above. , Monitoring Requirement (24) A. The temperature at the POD will be monitored once per hour during power MOoMATE #4 operations of Unit 3 utilizing the" manual address of thennistor buoy Station "E" of the Environmental Data Acquisition System. The temperature sensor 0 system has a range of 30 - 110 and an accuracy of 10.2%. B. When this buoy is inoperative temperatures from other buoys (upstream and downstream) in the discharge canal will be monitored. (8) C. When the data acquisition system is inoperative the tsoperature at the POD shall be estimated using operating and physical data in conjunction with curves generat-by an empirical analysis of the Crystal River discharge canal variables. (7,23 Bases '
- 24) 0 The 103 F effluent temperature during normal operations is established to assure that the affected area within the receiving waters is minimized.
l l l 2- 3 4 i
{ 2.1.3 Maximum 11 eat nelection Rates Not applicahic. 2.1.4 Rate of Change of Discharge Temperature
- '~~ ~~~ ~~
(So)
~
The Crystal River Unit 3 Final Environmental Statement, P. 5-19 addresses the effects of rate of change of discharge temperature. Harmful effects would be anticipated to occur from a temperature drop if all three units were to be shut down simultaneously with a loss of site power. How-ever, this situation would result in loss of all circulators and would
. result in a: gradual temperature decrease rather than a shock decrease. Thus, it is felt this limiting condition for operation is not applicable.
~~-
2.1.5 Heat Treatment of Circulating Water System Not applicable. 2.1.6 Deicing Operations Not applicable. 24
I 2.3 CHEMICAL Objective - To define the conditions for release of non-radioactive liquids and solids to the Gulf of Mexico to assure compliance with applicable State and local regulations and to ensure that the releases will not adversely affect public he.alth or the natural environment. All chemical discharges shall be treated to adhere to the Water Quality Standards set forth in the Rules
, of the Florida Department of Pollution Control Chapter 17-3, Polluttor of Waters, which requires that a 90% organic and inorganic removal factor be applied against the total untreated waste produced by a given plant. The combination of Crystal River Units 1, 2 and 3's chemical waste generation and control fall under this requirement.
2.3.1 Biocides D Objective 4*Mt. N To limit the amount and concentration ofiesidual chlorine discharged to the Gulf. Specification . W $4=k A k v. A. Chlorination of each of the condenser circulating pipes Ashall bc staggered to pre rent simultaneous treatment with chlorine. The n. i .u : r.or tra-ticr af ::::h:' H: i : * % " D ' :: .t_:.: y... (d B. 740 Tais ftsv.wi. cutatiwE Suau rao1 Eu.a.so 1.8 ppm nd A4 i M idadd*L. j C.o.* b sret. od M *Tet,sn. ( 3) C , Ins. FgdW # twuts4 ATWA SMau- r* *r EMc. Era M th4JTR$ pse. men.m fvt. s w vs. 2-6
~ -
Monitoring Requirement A. The continuous chlorine recorder shall be observed once each day on
~
days when chlorination is performed to verify that th sidual chlorine does not exceed 1.8 ppm in the individual condenser outict water boxes. B. When the chlorine analyzer and/or recorder are inoperative, a sample shall be taken of each affected water box weekly (during chlorination) and analyzedy S.: M:::tc:; , :i .; etz..d: d . th:de. C. The continuous chlorine analyzer shall be calibrated semi-annually. C Bases Residual chlorine has a potentially detrimental effect on the estuary. The chlorine demand of the seawater at Crystal River has a range of 0.6 - 1.8 ppm. Each of the four water box effluent pipes empties into the Unit 3 mix-o ing zone. As only one box is being chlorinated at a time at W~"'t: 4:1
** A hr 1 mus.'5 w dilution occurs) Effectively, this results in water having a maximum chlo-rine residual of 0.45 ppm mixing with an equal volume of water heving a minimum chlorine demand of 0.45 ppm and the almost immediate chemical reduction of the remaining chlorine. As each water box is being chlori-nated, a sample is taken from the outlet water box, analyzed for residual chlorine (free and combined), and the results are recorded on a circular re- '
corder. Sampics are automatically changed by solenoid valven in accordance with the sequence of the chlorine generation system. This system provides a continuous record of chlorine residual in each outlet water box. 2-7 l l l
.>.u-.'
4 i 2.3.2 Corrosion Inhibitors l[ [11) Not applicable. No chromates are in use at the Crystal River Plant site. Any other corrosion inhibitors after use are routed to the Chemical-Industrial l Waste pond which are monitored as described in Section 4.1.6. (53) 2.3.3 Suspended and Dissolved Solids l Suspended solid concentrations in the discharge canal, due to errosion will be measured as described in Section 6.4. Dissolved solids are monitored as 1 discussed in Section 4.1.6. (53) 2.3.4 g pH is monitored as discussed in Section 4.1.6. (53) 2.3.5 Other Chemicals Which Affect Water Quality Chanical releases anticipated from the plant with the exception of chlorine-treatment of the condenser cooling water (which is considered in item 2.3.1) are monitored as described in Section 4.1.6. Any boron discharge is due to the inefficiency of the condensate demineralizers; the maximtsn discharge con-centration is estimated to be 0.22 ppb of boron per liter of water discharged and the average concentration is estimated to be 0.022 ppb. I 2-8
t
~,- 1. The offluent control monitor shall be set to alarm and automat-ically close the waste discharge valvo prior to exceeding the limits spec-ified in 2.4.1A above.
caesp ,Mrseect Moanetsobe scre.arO naA D3,Sa/) 2. Liquid waste activity and flow rate shall be hrecorded during re-leasc . If this requirement cannot be met, continued release of liquid effluents shall be permitted only during the succeeding 48 hours pro-vided that during this 48-hour period, two independent samples of each tank shall be analyzed and two station personnel shall independently check valving prior to the discharge. D. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes, except laundry wastes, prior to their discharge when it appears that the projected cumulative discharge over a calendar quarter would exceed 1.25 curies, excluding tritium and dissolved gases. Laundry wastes will be
~
processed in the radwaste system if the groskhadioactivity concentra-tion leaving the Unit 3 mixing zone exceeds 1 x 10 bCi/ml. E. The maximum activity to be contained in one evaporator condensate storage tank that could be discharged directly. to the environs, shall not exceed 10 curies, excluding tritium and dissolved gases. F. When the release of radioactive effluents, excluding tritium and dissolved gaser, execeds 2.5 curies during any calendar quarter, the licensee shall notify the USAEC in accordance with specification 5.6.2.A. l l
?-10
; . -.. m .~ - -
.. Monitorino Requirement x
Arms IN A. Prior to release of each batch of liquid effluent, a samplo shall be taken from that batch and analyzed for gross ( B,y) radioactivity and the discharge concentration will be ca'culated using the circulating water flow rate at the time of discharge. The amount of major gamma-cmitting isotopes released will be determined byhr-'f+ in accordance with USAEC Regulatory (S*S) Guide 1.21 epitric Maussu a weis.3 c ep snr. m3 B. Records shall be maintained of the radioactivity concentrations, volumes before dilution of each batch of liquid effluent released, and average dilution flows and lengths of time over which each discharge oc-curred in accordance with Specification 5.7. C. The liquid effluent radiation monitor shall be tested and calibrated in accordance with Table 15-3, Item 23 of the FSAR.
, D. The performance of automatic isolation val'ves and discharge tank selection valves shall be checked annually.
Bases The specifications are based on the following criteria: (1) The potential ex-posure to the whole body or any organ of an individual in the unrestricted areas shall not exceed 500 mrem /yr, (2) the design objective is that the annual liquid release, excluding tritium and dissolved gases, should not exceed 5 Ci and (3) the annual average concentration of tritium in liquid wastes prior to release to unrestricted areas should not exceed 5 x 10~ "Ci/ml . It is noted that the USAEC analysis which was reported in the l'inal Environ-mental Statament for Crystal River Unit 3 indicates that a 5 Ci/yr release would result in a maximum individual off-site dose of less than 5 mrem /yr.
; -11
'4 h - the requirement that: Og /mpciR 2.6 x 10 , wherc Q is the measured rate g , of relecsc (Ci/yr) of isotope i and mpci is the maximum permisnibht con- !
l centration of radioactive isotope i as shown in Column 1, Tablo II of Append.x B to 10 CFR P$rt 20 (pCi/ml) .
-B. The release rate, Q7 of I-131 and particulates with half-lives greater than eight days will meet the requirement that: Q 211. Ci/yr.
7 O. Du' ring release of radioactive gases from the gas decay tanks, at least one of the redundant automatic isolation devices activated by con-tinuous air monitors shall be operating. D. During release of radioactive gases from the reactor building, the con-tinuous gross gas monitor which activates the automatic purge isolation de-vices will be operating. If inoperable, the containment atmosphere gross gas activity wlU be continuously monitored.
, E. The equipment installed in the airborne radioactive waste treatment-system will be maintained and will be operated when the relense rates exceed: (a) Two percent of specification 2.4.2. A, or (b) One percent of specification 2.4.2.B.
F. The maximum radioactivity to be contained in one gas decay tank will not exceed 3.5 x 10 C1. G. The release rates, averaged over any calendar quarter will not exceed 16 percent of the 2.4.2. A limit or 8 percent of the 2.4.2.B limit. H. If the release rates, averaged over any calendar quarter, exceed four percent of the 2.4.2. A limit or two percent of the 2.4.2.B limit then the
' licensee will notify the USAEC in accordance with specification 5.~6.2. A.
2 '.6 i .
I Monitoring Requirement A. The following measurements will be made on the reacter building and w auxiliary buthling qandous waste streams b',(.sc,
- 1) Theww em.23 gross m.o.a.a3 noble ru.ent gan radio-activity will be continuously monitored and recorded to provide Ci per unit volume of gas released, (2) the volume flow rate will be continuously moni-tored and recorded, (3) the radioactivity monitors will be calibrated in terms of Ci per unit volumes of gas or equivalent CPM at least once per quarter by means of a known radioactive source, and (4) at least one vent monitor on each of the effluent release streams will be operating, during power generation.
B. Samples of gas from gas decay tanks just prior to release and from the reactor containment just prior to purge will be teken and analyzed ac-cording to the schedule presented in Table 2.4-2. The release rates shall be based on the sample gross (p,y) . analysis, the waste gas decay tank volumes and pressures, and the containment purge rate. The total release [ ee4es of each isotope will be calculated C. A bypass stream from gaseous effluent streams will be routed con-tinuously through a series combination of a particulate filter and charcoal filter. These filters will be analyzed for radioisotopes according to the schedule given in Table 2.4-2. The total release rate of I-131 will be cal-culated from the ENN 'CO found on the filters, the sample flow rates and the gaseous effluent release rates. 2-17 l l l
~ ~^
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t TABLE 2.4-2 (Cont'd.) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANAL,YSIS SCHEDULE Sampling Detectable Sample Type Frequency Activity Analysis Concentration Charcoal Filter Weekly I-131 10~ pCi/cc
~
on Effluent By- Quarterly I-133, I-135 10 pCi/cc pass Stream Particulate Filter Weekly Gross S,y 1 x 10~ pCi/cc on Effluent By- Weekly Ba/La-140 1 x 10
~
poi /cc pass Stream Monthly ~II Gross S, y 1 x 10 gCi/cc Composite -10 Individual y, 1 x 10 Ci/cc of weekly Emitters samples Quarterly -11 Sr-89, Sr-90 1 x 10 pCi/cc 4 Composite of monthly samples
~
, One weekly Gross a 1 x 10 yCi/cc sample / quarter (1) Analysis shall also be made within one month of the initial criticality and following each refueling process change or other occurrence which could alter the mixture of radionuclides.
(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitivity limit when other nuclides are present in the sampic at much higher levels. Under these circumstances, it will be more appropriate to calculate the icvels of such radionuclides using observed ratios with those radionuclides that are measurable. (3) When the iodine or particulate release rate is greater than the release rato given in 2.4.2 $above, thi sample shall be analyzed daily until a steady release Invol han been . :tablished. (4)- Applicable for containment only luring continuous purging oncrations during extended maintenanco.
. 19
b cnnual average atmospheric dispersion factor in untentricted areas (sec/m ) . 3.15 x 10 in the number of seconds in n year and mpel is the maximum permissible concentration of radioactive isotope i in unrestricted arcas as defined in 10 CFR Part 20, Appendix B, Table II, Column 1. The values of Qg will be measured as described in monitoring requirement
-6 2.4.2.B. The applicable value of Y/Q is 1.22 x 10 sec/m according to the Crystal River Unit 3 Applicant's Environmental Report Docket No.
50-302. Rearranging and including the numerical value of X/Q yields, Q /mpc1R 2.6 x 10 . B. Specification 2.4.2.B requires that the concentration of I-131, due to the plant effluents, in any unrestricted area, not exceed 1/233 of the maximum permissible concentration specified in 10 CFR Part 20, which insures that the exposure rate will not exceed 1500 mrem /yr. Stated mathematically; Q 7 (x/Q)/3.15 x 10h mpeg/233, where Qg is the rate of release of I-131 (Cl/yr), (X/Q) is the applicable maximum annual average atmospheric dispersion factor in unrestrir* )d areas (sec/in ), 3.15 x 10 is the number of seconds in a year and mpci is the maximum permissible concentration of I-131 in unrestricted areas as defined in 10 CFR Part 20, Appendix B, Tablo II, Column 1. Q will be measured as described in monitoring requirement'2.4.2.C. The applicabic value of (Y/Q) for any unrestricted area is 1.22 x 10" sec/m as described in Specification 2.4.2. A. The value of mpc} (fro- 10 CFR
-10 Part 20) is 1 x 10 C1/ml .
4
'- !-21
.-~
e f
- Xe-133 for which Ey has a value of 0.0728 and Fg has a value of 0.126 MEV . Rearranging the ,above equation and inserting the numerical values, including 0.5 rem / year for the maximum value of D, yields, Q R 3.5 x 10 Ci.
G. Specification 2.4.2.G requires that the release rates, averaged over any calendar quarter, not exceed eight times the design objective values. The factor of eight over the design objective will result in quarterly average airborne concentrations in unrestricted creas which are small percentages of the limits specified in 10 CFR Part 20 and also provides operating 1 flexibility so that the public may be provided with a dependable source of power under unusual conditions. H. Specification 2.4.2.H requires that the USAEC be notified if the release rates, averaged over any calendar quarter, exceed twice the design objective values. Reporting releases of a factor of two over the
' design objective values will insure thatteleases of this magnitude will be of genuine concern and also provide some operating flexibility. - 2 2 L I. Monitoring requirements 2.4.5. A, 2.4.4.B, and 2.4.M3 insure that the essential information with which to carry out the specification will be available.
2. J. Monitoring requirement 2.4.4.D stipulates that periodic tests of automatic isolation be done to demonstrate their ability to perform. Z.- K. Monitoring requirement 2.4.4.E stipulates that records of concen.tra-
-tions and volumes released should be available for future reference.
W s ' .23
the dist:hanic canal which is about one and one-half milen lon<1, 125 0
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f7) wid" anri dredged to 10 f t. below n"mn low water. A spoil bank or dite a sw a ** F.3nt L78 extends a further mile from the shore into the Gulf A Water velocity in the
. discharge canal has bnen calculated to be 2.4 ft./sec. Transit tim" f rom the generating plants to the discharge point will be approximately 1 br.
At the discharge point, the heated cooling water mixes with water from the Gulf. 3.3 CHEMICAL USAGE Mm (17) Table 3.3-1 presents the estimated Aamounts of chemicals to be used M Pia.rr cite and that will be ultimately discharged from the plant. The industrial waste-water collection pond will sarvice these wastes, except for the lime sludge (which is handled as described in Section 3.5). Percolation from the ponds will provide separation and treatment. Test wells are located around the ponds for testing groundwater to asstre compliance with applicable State of Florida water quality standards. 3.4 WATER TREATMENT SYSTEM With the exception of sea water for condenser cooling, all water used at the Crystal River Plant comes from Plorida Power Corporation shallow wells located about four miles east of the plant. In 1970,161,000,000 gallons were drawn from these wells. All of this water is processed through the plant water treatment system lime softener and anthracite filters before use. This " treated water" is the potable water use'd for all plant functions except stearr generator make-up.
~-
{ TAllLI: 3.3-1 CHEMICAL USAGE N Altesid a Chemical Source or Purpose A nual IJ man l Pli(mphate (l'0 ) lloller lilowdown 8% lim. 4 , Caustic boda (NaOli) Domineralizer Regenerate 593,050'bs. Hydrazine Oxygen Scevenger 237!bs. Lime - Water Softec ig 400,000 lbs . NaZnPO Water Softening 3,338 lbs . 4 Cyclohexamine Condensate pH Control 220 gal. Sulfuric Acid (H2SO4) Demineralizer Regenerate d Units 1 and 2 120,120 gal. ; Unit 3 Makeup Demineralizer 36,500 gal. Unit 3 Condensate Polishing Domineralizer 243,670 gal. Ammonia Boiler Blowdown, Condensate PolisF ag 730 gal.
. POW #671, Polyelectrolyte Ceagulant Aid 91lbs.
:2:: "7;::: '.: 't * "' M :: 2: ^^?'t:.
Dilute Hydrochloric Acid (hcl) Boiler Cleaning 15,000 gal. Ethylene Diamino Tetracetic Acicl' (EDTA) Acid Cleaning 8,000 cal. Rodine 31A Acid Cleaning (Stabilizer) 20 gal. Synthetic Insulating Fluids (Askarels and Intertcon) and. Normal Transformer Oils Transformers < 100 gal. CS (Calgon Corrosion Closed Cooling System Inhibitor Control) (Units 1 and 2) 1,000 lbs.
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=-
quadrats, by sediment cores, and by venturi pumps. The number, ' frequency and location of samples to be taken will be determined from (gg) a statistical analysis of the research presently being conducted in this aren..SMA.as wit.a. AE 9 fu7s Fiso 84 Ar. DANTE Op** e.*AMC , Productivity and respiration of the system will be determined by the methods currently employed in the modelling work. Reportino Requirement Any changes in biomass, productivity or respiration beyond 2e of that a measured during preoperational monitoring will be rept.rted in accordance with 5.6.1. Bases In the discharge. area adjacent to the canal the productivity, respiration
, and biomass should increase due to an increased temperature of the cooling water. -If the opposite occurs and any of these parameters
( 30 ) decrease below\2d of that measured during preoperational monitoring, the systems should be investigated for catastrophic results. 4.1.3 hfarsh Grass Objective The purpose of this program is to measure the condition of the salt marsh adjacent to the discharge area. 4-5
a.- - l l (18.27, 4.1.6 CHEMICAL - INDUSTRIAL WASTE WATER TREATMENT SYSTEM ! 52,53) i OBJECTIVE To monitor the Chemical-Industrial Waste Water Ponds, and surrounding environs. SPECIFICATION Representative samples are to be obtained and analyzed once per month from test wells 1,4,5, and 6, the discharge canal directly to the North of the ponds, and the ponds themselves. (SeeFigure4.1.6) Samples are analyzed for pH, Nitrate (NO 3
), Sulfate (50 4), Phosphate (PO),
4 Iron (F),dissolvedsolids, E Copper (Cu),andZinc(Zn). REPORTING REQUIREMENTS Reports will be furnished in accordance with Section 5.6.1. BASIS Monitoring is perfonned to assure that applicable water quality standards are not violated. 1
i a 1 l l l
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TURNING BASIN Figure 4. l . 6 Settling Ponds a- Test Well Locations
4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING The liquid and airborne radioactive effluents will be monitored, controlled and audited as specified in Section 2.4. The radiological environmental monitoring program will provide information which can be used to assist in assessing the type and quantity of radiation exposure in unrestricted area resulting from plant operation. Environmental media which are sampled and analyzed for radioactivity are shown by the two diagrams on Figure 4.2-1. Each box in the diagrams contains the name of an environmental media which is sampled. The upper diagram shows the critical pathways; the lower diagram shows the other monitored pathways. Preoperational radiological environmental monitoring programs, to establish baseline environmental concentration values, were initiated in mid-1970. One program was operated by the State of Florida Department of Health and Rehabilitative Services; another program was operated by the University of Florida. The overall program is outlined on Table 4.2-1. The critical pathway monitoring program which is included in Table 4.2-1 is also shown in Table 4.2-2. Sample station locations are described on Table 4.2-3 and shown on maps on Figures 4.2-2 and 4.2-3. Typical l minimum detectable concentration values are given on Table 4.2-4. I \ A-lO
s A summary of the preoperational surveillance results is shown on Table 4.2-5. This summary includes median values of the observed environmental concentrations and 95 percent 1, "alues (i.e., values which exceed 95 per cent of all the comparable measured values). These values will be taken as the preoperational baseline concentrations. The 95 percentile values indicate the random frequency of high measured values during the preoperational program and also the random frequency of high values which can be expected during operation if the plant operation contributes negligibly to the environmental radioactivity. These 95 percentile values will be used during operation to assess the probability that any observed high concentration value is due to random fluctuations in measurements rather than to a true increase in environmental concentrations. l i 1
'4 - Il G
9
TABLE 4.2-1 GENERAL PATHWAY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPAM Pathway Sample Sample Sampling / Collection Analysis Significant Type Stations Frequency Routine Radionuclides Air External C04,C07,C09 Continuous / Quarterly TLD Xe-133, KR-88 Submersion Radiation C18,C24,C40 C41.C42,C43, C14H,C14M, C14G,C46 Air Air C04,C07,C18 Contimis/ Weekly Gross B and I-131 Inhalation C24,C40,C41 I-131 weekly, C46 y-spectral on monthly composite, Sr-89,90 of quarterly composite Precipita- Total C04,C24,C40 Continuous / Monthly H-3, y-spectral Cs-134,Cs-137,H-3 tion Deposition analysis I-131 Sea Water Water C01,009,C13 -- Monthly y-spectral analysis, Cs-134,Cs-137,I-131 (15) Cl4H,Cl4N,Cl4G A Within 8 hours of beginning composite for Sr-89, discharge of evap. condensate 90,H-3 quarterly storage tanks River Water Water C15 Quarterly H-3, y-spectral Cs-134,Cs-137,I-131 analysis Ground Water Water C44 Semi-Annual y-spectral Cs-134,Cs-137,I-131 Analysis H-3 H-3 Potable Water C07,C10,C18 Quarterly
- Extended y-spectral Cs-134,Cs-137,I-131 Water Analysis, H-3 H-3 Shoreline Bottom C01,C09,C14H Semi-Annual
- Extended y-Spectral Cs-134,Cs-137,I-131 External & Sediments C14M.C14G Analysis; Sr-B%9o Sea Food Chain
*See Table 4.2-4
/
TABLE 4.2-1 (Cont.) Pathway Sample ' Sample Sampling / Collection Analysis Type Significant Stations Frequency Routine Radionuclides Sea Food Marine C29,C30 Semi-Annual
- Extended y-Spectral I-131.Cs-134,Cs-137 Chain Plants Analysis Sr-89,90 I-133 (Marco Algae and submeryd Sea Plants)
Ingestion Crab C29,C30 Seni-Annual y-Spectral Cs-134,I-131.Cs-137 Crab Analysis
/
Ingastion Carnivorous C29,C30 Semi-Annual or in y-Spectral Cs-134,I-131 Cs-137 Fish Fish Season Analysis Ingestion Herbivorous C29,C30 Semi-Annual or in y-Spectral Cs-134,I-131 Cs-137 Fish Fish Season Analysis Ingestion Oysters C29,C30 Semi-Annual y-Spectral Cs-134,I-131.Cs-137 ' Oysters Analysis 1 Ingestion Shrimp C28 Semi-Annual y-Spectral I-13,Cs-134,Cs-137 Shrimp Analysis Ingestion Milk C05,C47 Monthly I-131 Analysis: I-131 Milk
- Extended y-Spectral Analysis, Sr-89.90 Ingestion Small C45 Semi-Annual y-Spectral I-131 Animals Terrestrial Analysis Animals Food Chain Vegetation C05,C40,C41 Semi-Annual y-Spectral I-131 (grasses) Analysis Ingestion Food Crops C19 Annual or at harvest y-Spectral I-131 Food Crops (Citrus) Analysis Ingestion Food Crops C04 Annual or at harvest y-Spectral Food Crops y_)33 (Watermelon) Analysis
' *See Table 4.2-4 4 -13
TABLE 4.2-1 (Cont.) : Pathway Sample Sample Sampling / Collection Analysis Type Significant Stations _ Frequency Routine Radionuclides
$9 . .
Food Chain Soil C04,C07,C18 First year, then every
- Extended I-131 Cs-137,Cs-134 ft) - C24,C40,C41.C46 Third- Spectral Sr-89,90 Fcod Chain Meat One sample within y Analysis, Sr-89,90 10 mi. of plant Semi-Annual Spectral Analysis Cs-137,Cs-134 ood Cha 4 Poultry & One sample within Semi-Annual Spectral Analysis Cs-137, Cs-134 Eggs 10 mi. of plant
/
*See Table 4.2-4 4'
4 4 i i 4-I4
, < k D
~
TABLE 4.2-2 CRITICAL PATHWAY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Pathway Sample Sample Sampling / Collection Analysis
- Critical Type Stations Frequency Routine Radionuclides Air External C14H,C14M, Continuous / Quarterly TLD Xe-133,Kr-88 Submersion Radiation C14G Air Air C41 Continuous / Weekly I-131 Analysis I-131 Inhalation -
Ingestion Milk C05 Monthly I-131 Analysis I-131 Milk Ingestion Crab C29 Semi-Annual y-Analysis Cs-134,Cs-137 Crab I-131 Ingestion Fish C29 Semi-Annual in Season y-Analysis Cs-134,Cs-137, Fish I-131 Sh: reline Bottom C14H,C14M, Semi-Annual y-Analysis Cs-134 Cs-137 External Sediments C1% Boating, Sea Water C14G Monthly y-Analysis Cs-134,Cs-137, Swimming I-131 External
*Nuclides which contribute at least 70%
of dose in the pathway 4-l5
S TABLE 4.2-3 SAMPLE STATION LOCATION (Cont'd.) Station Direction from Direction from Number Loca tion plant (miles) plant C28 Ralston Purina Research 0.5 W Pacility between Intake and Discharge Canals C29 Discharge Area 2.0 W C30(b) Intake Area 3.0 WSW C40 On site near N.E. 2.5 ENE Boundary at excavated pond and pump station C41 On-site meteorological 0.4 SSW tower C42 Mid-way out discharge 1.2 W canal on S. side C43 S.E. corner Holland 1.6 NW Ranch C44 On-site well supply to 0.2 E plant softener C45 On-site along main 1.3 ENE access road g (3er-) C46 N.E. Corner of site boundary C47 Gainesville (U.F. Dairy) 80 (a) C14H refers to a station at the head en '. of the discharge canal: C14M refers to a station midway between the ends of the canal: Cl4G refers to a station at the Gulf of Mexico end of the canal. j ( 37) (b) This station is considered as background station for marine sampling. g 4-16 I
y TABLE 4.2-3 SAMPLE STATION LOCATI NS Station Distance from Direction from Number Location plant (miles) plant C01 Levy County Park 7.2 NNE West end State Road 40 C04 Sec. 7T17 State Road 17E 6.9 NE State Park Old Dam on River C05 Holland Ranch 2.3 NE S24T24SR16E C07 Crystal River Public 7.5 ESE Water Plant C09 Citrus County Park 5.0 SSE END SR44 R16 ET 18S C10
~
Indian Waters Public 4.9 SE Water Supply Cl3 Mouth of Intake Canal 2.6 WSW C14
- Discharge Canal 1.4 W CIS Withlacoochee River 5.9 N Yankeetown Dock Isaac Walton Lodge C18 Yankeetown City Well 5.8 N C19 NW Corner SR448 12.6 NE C24 City of Inverness 25.3 SW Public Water Supply 4-17 t
2-> _ l' ( 33) . AIRSORNE RELEASES LIQUID RELEASES ( AIR ERTE4NAL RA DI ATION SEA WATER PORatt SE0lWENTS CRUSTACKA
<r MILE FISM -
CRITICAL PA T N W AYS AIRBORNE RELEASES LlOU10 RELEASES T l AIR SEA WATER
+ v d l 4 , 1 1 4 & 1 S 4
& OIL h FOR AGE CROPS 4 PRECIPIT ATION j 4 E R A01 AT10 N
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WATER w ER v ' u ( w w b l d ! TERRESTRIAL l wlLDLIFE V ;' _ _. J . . S_ ._ . __ V V L9 OTHER MONITO RE D PA TM w a t h Figure 4.2 - r Environmental Media and Exposure Pathways 4-It
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i Figure 4.2 2 Off Site Sample Station Locations 4-IT J
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s TABLE 4.2-4 TYPICAL MINIMUM DETECTABLE CONCENTRATIONS Gross In air 1 pCi/m By Means of Spectral Analysis Mo99m 10 pCi/1* Co-58 , 10 pCi/1 Ba-140 10 pC1/1 Cs-134 10 pCi/1 Cs-137 10 pCi/1 Zr-95-Nb-95 10 pCi/1 I-131 10 pCi/1 Tritium Unenriched 200 pCi/1 Enriched 30 pC1/1 Strontium Sr-89 5 pCi/1 Sr-90 2 pCi/1 I-131 In air 0.06 pCi/m3 In milk 0.5 pCi/1 External Radiation Z o mrem /yr.
- Units of pCi/1 pertain to media of unit (1g/ml) density 4l~d? l .
1
rx Table 4.2-4 TYPICAL MINIMUM DETECTABLE CONCENTRATIONS (Con.'t) Extended Canuma Spectral Analysis (GeLi-Typical) Cr-51 60 pCi/1* Mn-54 10 pCi/1 Fe-59 20 pCi/1 Co-58 10 pCi/1 Co-60 10 pCi/1 Rb-86 100 pCi/1 Rb-88 80 pCi/1
-191m .
10 pCi/1
-92 150 pCi/1
-93 100 pCi/1 Zr-95 20 pCi/1 i Mo-99 80 pCi/1 Tc-99m 10 pCi/1 Te-129m 70 pCi/1 Te-129 70 pCi/1 Te-132 10 pCi/1 I-130 10 pCi/1 I-131 10 pCi/1 1-132 10 pCi/1 I-133 10 pC1/1 I-134 10 pCi/1 I-135 40 pCi/1 Cs-134 10 pCi/1 Cs-136 10 pCi/1 Cs-137 10 pCi/1 Cs-138 20 pC1/1 Ba-140 30 pCi/1
'*Nnits of pCi/1 pertain to media of unit (Ig/ml) density 4 - z.z.
, ~ . ,.
TAltl.l: 4.2-5
\
SUMMARY
OF PREOPERATIONAL I:NVIR()NMENTAL SURVflLLANCE RESULTS 1971 l974 Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Water, Potable Gross (a) 19. pC1/1 H-3 (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 ., (a) (a) Zn-65 (a) (a) Mn-54 (a)' (a) I-131 (a) (a) Water, Surface Gross (a) 19. pCi/l H-3 (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 (a) (a) Zn-54 (a) (a) Mn-5 4 (a) (a) I-131 (a) (a) Water, Precipitation Gross (a) 13. pC1/1 H-3 (a) (a) Co-58 (a) (a) Co-60 (a) (a) Ba-140 (a) (a) Cs-134 (a) (a) Cs-137 (a) (a) Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) s 4-2S
s TABLE 4.2-5
SUMMARY
OF PREOPERATION ENVIRONMENTAL SURVEILLANCE RESULTS 1971 1974 (Cont'd.) Preoperational Concentrations Environmental' Media Nuclide Median Value 95 Percentile Value Sea Water H-3 71. pCi/l (b) Ba-140 (a) 11. pCi/kg Cs -137 * (a) -
- 10. pCi/kg Zn-65 (a) 7. pCi/kg Mn-54 (a) (a)
I-131 (a) (a) K-40 0:18 g/kg - 0.44 g/kg Ra-226 (a) 600, pC1/kg-Th-232 (a) 7. pCi/kg Zr-95 (a) (a) Ru-106 (a) (a) Air Gross ji 0.029 pCi/kg 0.120 pCi/kg3 Ba-140 (a) 0.016 pC1/m Cs-137 (a) 0.013 pCi/m 3 Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) 0.004 pCi/m K-40 (a) (a) - Ra-226 (a) 0. 24'1.pCi/mj Th-232 - (a) 0.008' pCi/m 3 Zr-95 0.003 pCi/m3 0.04.3 pCi/m Ru-106 0.025 pCi/m3 0.216 pC1/m 3 Ce-14 4 - - 0.003 pct /m} O.172 pCi/m 3 Milk Sr- 4. pCi/l 6. pCi/l Cs-13 (a) (a) 1-131 (a) (a) Ba-140 (a) (a) Co-58 (a) (e) Co-60 (a) (a)
'Mn-54 (a) (a)
Zr-95 (a) (rd Cs-137 (b) ' N,, _ 4 L
. . - .~ - - -
TABLE 4.2-5
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971- 1974(Con. 't) Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Soil Ba-140 .(a) (a) Cs-137 270. pCi/kg 1100 pCi/kg Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) K-40 (b) (b) Ra-226 (a) 2200. pCi/kg Th-232 (a) 330. pCi/kg Zr-95 40. pCi/kg 150. pCi/kg ; Ru-106 0. pCi/kg 330. pCi/kg ' Small ' Terrestrial Ba-140 (a) (a) Animals Cs-137 (a) 80. pCi/kg Zn-65 (a) 160. pCi/kg Mn-54 (a) (a) I-131 (a) 100. pCi/kg K-40 3.17 g/kg 4.28 g/kg Ra-226 (a) 720. pCi/kg Th-232 (a) (a)
" Zr-95 (a) 70. pCi/kg Ru-106 (a) (a)
Total Deposition Ba-140 3 pCi/m2-day 22 pCi/m2-day Cs-137 (a) 6 pCi/m2-day Zn-65 (a) 7 pCi/m2-day Mn-54 (a) (a) I-131 (a) (a) K-40 (a) .03 g/m2-day Ra-226 20 pCi/m2-day 508. pCi/m2-day Th-232 (a) 6. pCi/m2-day Zr-95 (a) 13. pCi/m2-day Ru-106 (a) 152. pCi/m -day 4-25
o-TABLE 4.2-5
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL. SURVEILLANCE RESULTS 1971- 1974 (Cont'd.) Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Oyster Meat Ba-140 (a) (a) Cs-137 (a) (a) Zn-65 (a) 33. pC1/kg Mn-54 (a) (a) I-131 (a) (a) , K-40 (a) 2.2 g/kg ' Ra-226 (a) 534. pCi/kg Th-232 (a) (a) Zr-9 5 (a) (a) Ru-106 (a) 82. pCi/kg (a) Blue Crab Ba-140 (a) 55. pCi/kg Cs-137 (a) 75. pCi/kg Zn-65 (a) 127. pCi/kg Mn-54 (a) 24. pCi/kg I-131 (a) (a) K-40 1.7 g/kg 2.4 g/kg * ' - t Ra-226 1325. pCi/kg 3600. pC1/kg Th-232 92. pCi/kg - 170. pCi/kg Zr-9 5 (a) 13. pC1/kg Ru-106 (a) (a) - Herbivorous Fish Ba-140 (a) 50. pCi/kg
f '
Cs-137 (a) 110. pC1/kg Zn-65 (a) 63. pCi/kg Mn-54 (a) (a) I-131 (a) . (a) K-40 2.6 g/kg 3.7 g/kg Ra-226 960. pCi/kg 3100, pCi/kg Th-232 (a) 84 pCi/kg Zr-95 (a) 9. pC1/kg Ru-106 (a) 90, pCi/kg 4-25
TABLE 4.2-5
. t.
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971 19M (Con't) Preoperational Concentrations , Environmental Media Nuclide Median Value 95 Percentile Value Carnivorous Ba-140 (a) 72. pCi/kg Fish Cs-137 (a) 43. pCi/kg Zn-65 (a) 99. pC1/kg M'n -54 (a) (a)
. I-131 (a) (a)
K-40 2.8 g/kg 4.6 g/kg Ra-226 335. pCi/kg 2400. pCi/kg Th-232 . (a) 92 pCi/kg Zr-95 (a) 12. pCi/kg Ru-106 (a) (a) Shrimp Ba-140 (a) (a) Cs-137 (a) 37. pCi/kg 2n-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) K-40 1.1 g/kg 3. g/kg Ra-226 (a) (a) Th-232 (a) 36. pCi/kg Zr-95 (a) (a) Ru-106 - (a) (a) Food Crops 0o-58 (c) (Oranges) (a) Co-60 (a) (a) Ba-140 (a) (a) Sr-90 105. pCi/kg 130. pCi/kg Cs-134 (a) (a) Cs2137 (a) (a) Zn-65 (a) (a) Mn-54 (a) (a) I-131 (a) (a) N, . 4- 27
--ce ,. . .. , TABLE 4.2-5 SUPNARY OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971 1974 (Con. 't) Preoperational Concentrations Environmental Media Nuclide Median Value 95 Percentile Value Vegetation K-40 .69 g/kg 2.9 g/kg Ra-226 (a) 2363. pCi/kg Th-232 (a) 120. pCi/kg Ba-140 26. pCi/kg 253. pCi/kg Zr-95 (a) 31. pCi/kg Cs-137 1363. pCi/kg
~
5416. pCi/kg Zn-65 (a) 589. pCi/kg Mn-54 (a) (a) 1-131 (a) (a) Ru-106 (a) (a) Aquatic Plants Ba-140 (a) 75. pCi/kg and Crasses Cs-137 (a) 181. pCi/kg (Including Algae Zn-65 (a) 156. pCi/kg and Plankton) Mn-54 (a) 43. pCi/kg I-131 (a) 37. pCi/kg K-40 1.8 g/kg 15. g/kg Ra-226 624. pCi/kg 3300. pCi/kg Th-232 . (a) 280. pCi/kg Ru-106 (a) 360. pCi/kg Zr-95 18. pCi/kg 157. pCi/kg External Radiation All 62. rem /yr (b) Ocean Sediment Ba-140 (a) (a) Cs-137 (a) 250. pCi/kg 2n-65 (a) (a) Mn-54 (a) 19. pCi/kg I-131 (a) 34. pCi/kg K-40 .31 g/kg 1.2 g/kg Ra-226 2900. pCi/kg 10000. pCi/kg Th-232 90. pCi/kg 300 pCi/kg Ru-106 190. pCi/kg 690. pCi/kg Zr-95 12. pCi/kg 40. pCi/kg 3 L
-f-29
TABLE 4.2-5
SUMMARY
OF PREOFERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971- 1974 (Cont'd.) (a) - The median value is less than the minimum detectable value; no median value is given. (b) No value is available at this time.
,(c) In some cases the values listed are smaller than the minimum detectable value.
Note: Prior to reactor startup, median u.alues will be provided for the
< radionuclides for each environmental media classification listed or: Table 4.2- or values of zero will be assumed.
A e 4 .21 ,
) Table 4.2-6 presents the anticipated maximum concentration increases in the critical pathway and other media for the design releases. The guidelines for these values are that limits in dose rate in unrestricted areas due to Crystal River Unit 3 operation are as low as practicable but should not exceed a 5 mrem /yr incremental increase in dose rate from radionuclides except I-131 and that the incremental thyroid dose increase from the plant's release of I-131 should be 1csa than
- 15 mrem /yr. All of the values listed in Table 4.2-6 were derived from the design release values listed in the " Final Environmental Statement" (Crystal River Unit 3) and the dose models in Wash 1258.
The lists of nuclides considered for determination in the environmental media include all that are anticipated from a design liquid and gaseous release even though most will produce concentrations far below detection limits. The design objectives of the Crystal River Unit 3 plant (insofar as environmental media concentrations are concerned) are that the radioactivity concentrations in the environment in the vicinity of the Crystal River Plant, assuming that radioactivity from sources other than the Crystal River plant are insignificant, should not exceed, over a long term, values greater than the preoperatic,nal baseline median concentration values plus the maximum concentration increase for design release values on Table 4.2-6. The operational surveillance program shall consist of: (1) a continuation of the program of measurements of radioactivity in environmental media which is outlined in Table 4.2-1, (2) reporting all the results of this program on a routine basis as described in Section 5.6.1 and (3) reporting the results of measurements of 5-4- So p i
radioactivity in critical pathway environmental media samples on the non-routine bases described in Section 5.6.2. The critical pathway environmental media are air, crab, fish, sediment, sea water, milk and external ganna radiation. Detailed specifications may be divided into three major groups: (1) milk (and/or green leafy vegetable samples); (2) all other media, because of the basic differences in reporting requirements for I-131; and (3) external ganna radiation. 4.2.1 Media Other Than Milk, Green Leafy Vegetables or External Radiation Objective The objective is to monitor radioactivity in the critical and indicator media in the vicinity of the plant to acquire and report infonnation which may assist in the assessment of the radiation dose to man due to the plant operation. Specification Samples will be taken from locations and at frequencies, listed in Table 4.2.1, and will be analyzed according to the routine listed in Table 4.2-1 using procedures which will provide concentration values ' with minimum detectable limits which are equal to or less than those listed in Table 4.2-4. Both the preoperational environmental surveillance results (Table 4.2-5) and the maximum expected concentration increase due to the design releases (Table 4.2-6) have been sunnarized. The control station k-3)
p value for each media, radioisotope and station will be defined as either [ (1) the upper 95%' percentile value from the preoperational program plus the expected increase due to design releases or (2) the upper 95 percentile value from operational stations outside of the plant's influence, whichever is larger. Reporting Requiren ts
- 1. If, during any six-month report period, a measured level of radioactivity in any of these environmental media exceeds four times the control station value, a written notification will be submitted within 30 days advising the AEC of this condition.* This notification should include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
- 2. If, during any six-month report, a measured level of radioactivity in any of these environmental media exceeds ten times the control station value,
, a written notification will be submitted within one week advising the AEC i
of this condition.* This notification should include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result. Bases The basis of the specification is that radioactivity concentrations will be determined by direct analysis'of the environmental media. The basis
*In the case of a tentatively anomalous value for radiostrontium, a confirmatory re-analysis of the original, a duplicate or a new sample may be desirable. In this instance the results of the confirmatory analysis shall be completed at the
! earliest time consistent with the analysis, and if the high value is real, the' report to the AEC shall be submitted within one week following this analysis. 4-1z. l l
g e of the reporting requirement is that concentration values which may ( be significantly above the control station value will be reported non-routinely; all results will be reported routinely. Selection of samples, stations, and analyses has been based on FES design releases and WASH-1258 model transport parameters. 4.2.2 Milk and Green Leafy Vegetables Ob.iective The objective is to monitor radionuclide concentrations in milk produced in the vicinity'of the plant to acquire and report information which may assist in the assessment of the radiation dose to man from ingestion of milk due to plant operation. Specification ( Samples of milk will be taken from locations and at frequencies listed in Table 4.2-1 and will be analyzed according to the routine listed in Table 4.2-1. Analysis will be carried out within eight days (one I-131 half-life) of sampling. Suitable analytical procedures will be used to determine the radioiodine concentration to a sensitivity of 0.5 picocuries per liter of milk at the time of sampling. For activity levels at or above 0.5 picorcuries per liter the overall error (one sigma confidence level) of the analysis will be within
+ 25%. Results will be reported, with associated calculated error, as picocuries of I-131 per liter of milk at the time of sampling.
If for any reason, milk samples listed in Table 4.2-1 are not available, green leafy vegetable samples will be substituted for the above milk specificiation. The time of analysis should be similar to milk samples 1 3
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however, the overall error should be within + 50%. All deviations r ( from the sampling schedule shall be described in the semi-annual reports. h) A semi-annual census of milk animals and food crops shall be conducted to determine their location and number, within 10-mile radius of the plant site, using reference infonnation from such as county agricultural agents or other reliable sources. Reporting Requirements
- 1. If milk samples collected over a calendar quarter show average concentrations of 4.8 picocuries per liter or greater, a plan shall be submitted within thirty (30) days advising the AEC of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any individual.
- 2. If individual milk samples show I-131 concentrations of 10 picocuries per liter or greater, a plan shall be submitted within one week advising the AEC of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any individual.
- 3. If green leafy vegetable samples collected in lieu of milk over a calendar quarter show average concentrations of 220 picoeuries per kilogram or greater, a plan shall be submitted within thirty (30) days advising the AEC of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any individual.
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,' 4. If individual green leafy vegetable samples collected in lieu of milk show I-131 concentration of 440 picocuries per kilogram or greater, a plan shall be submitted within one week advising the AEC of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem /yr to the thyroid of any individual.
Basis A concentration of 2.4 picocuries per liter of milk will result in a dose to the thyroid of an infant (2 gram thyroid) of 15 mrem per year, based upon the consumption of one liter per day of fresh milk for the year. Concentrations of 110 picocuries per kilogram of green leafy vegetables will result in a dose to the thyroid of an adult of 15 mrem /per year based upon the annual consumption of 72 kilograms. 4.2.3 External Radfition' Objective The objective is to monitor the external radiation in the vicinity of the plant to acquire and report information which may assist in the assessment of the ambient radiation dose to man in unrestricted areas due to plant operation. Specification Ambient external radiation levels will be measured at locations and frequencies listed in Table 4.2-1 using procedures which will provide raditation level values with minimum detectable increases over pre-operational mean background which are equal to or less than that listed in Table 4.2-4. 4-35
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t l 1 1 Reporting Requirement The results will be reported in routine reports in accordance with Section 5. 6. 1, Basis t The basis of the specification is that external radiation in the vicinity of the plant will be measured directly to ensure that the total body dose to the general public will be as low as practicable. l l i i
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. TABLE 402-6 MAXIMUM CONCENTRATION INCREASES POR DESIGN RELEASES f
'I Environmantal Nuclide Media Concentration Increase Air Gases Kr-83m 5.0 pCi/m 3 (Discharge Canal) Kr-85m 25. pCi/m3 Kr-85 1700. pCi/m3 Kr-87 15. pCi/m3 Kr-88 45. pCi/m3 Xe-131 47. pCi/m 3 Xe-133m 55. pCi/m3 Xe-133 5600. pCi/m 3 Xe-135m 50. pCi/m 3 Xe-138 9.9 pCi/m 3 I-131 0.31 pCi/m 3 I-133 0.08 pCi/m 3 Air None Particulates Milk I-131 .38 pCi/m 3 (4 miles ENE) I-133 .014 pCi/m 3 Grasses I-131' 7.3 pC1/m3 Vegetables, I-133 .25 pC1/m3 (.9. miles ENE) External Gamma 2.2 mrem /yr. Radiar. ion (Discharge Canal)
. 4-37 -
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TABLE 4.2-6 r (- MAXIMIM CONCENTRATION INCREASES FOR DESIGN RELEASES (Con't.) Environmental Nuclide Concentration Increase (pCi/kg) Media Fish Crab Shrimp Algae Sea Life H-3 380. 380. 380. 380. (Discharge Cr-51 .0046 .046 .046 .046 Canal) Mn-54 .056 .19 .94 .19 Fe-55 .061 .24 1.2 .37 Fe-59 .013 .05 .25 .076 Co-58 .061 6.1 .18 .061 Co-60 .0061 .61 .018 .0061 Rb-86 .023 .038 .0076 .0076 Rb-88 .5 .84 .17 .17 Sr-89 .00002 .00002 .00002 .00004 Y-90 .0035 .012 .012 .035 Y-91m .0018 .0061 .0061 .018 Y-91 .93 3.1 3.1 9.3 Y-92 .0029 .00095 .00095 .0029 Y-93 .00049 .0016 .0016 .0049 Zr-95 .0001 .00034 .00034 .0034 Nb-95 .00038 .00076 .00076 .00038 Mo-99m .53 5.3 5.3 5.3 Tc-99m .031 .31 .31 3.1 Te-127 .00017 .00017 .0017 .017 Te-127m .00017 .00017 .0017 .017 l Te-129m .0015 .0015 .015 .15 Te-129 .00096 .00096 .0096 .095 Te-131m .000088 .000088 .00088 .0088 Te-132 .0029 .0029 .029 .29 I-130 .0053 - .026 .026 2.6 I-131 15. 76.' 76. 760. , I-132 .74 3.7 3.7 37. 1 I-133 2.3 11. 11. 1100. I-134 .0076 .038 .038 3.8 [ I-135 .24 1.2 1.2 120. , Co-134 13. 21. 4.2 4.2 l Cs-136 3.3 5.5 1.1 1.1 l t Co-137 10. 17. 3.5 3.5 l j Cs-138 .061 .1 .02 .02 t l Ba-140 .000046 .000046 .000046 .0015 l
- 1 4-39
TABLE 4.2-6 MAXIMUM CONCENTRATION INCREASES FOR DEISCN RELEASES (Con.'t) Environmental Media Nuclide Concen*cration Increases Sea Water H-3 380. pCi/1 (Discharge Cr-51 4.6x10-5 pCi/1 Canal). Mn-54 .00002 pCi/1 Fe-55 .00006 pCi/1 Fe-59 .00001 pCi/1 Co-58 .0006 pCi/1 Co-60 .00005 pCi/1 Rb-86 .0008 pCi/1 Rb-88 . .017 pCi/1 Sr-89 .00002 pCi/1 Y-90 .00012 pCi/1 Y-91m .00006 pCi/1 Y-91 .031 pCi/1 Y-92 .00001 pCi/1 Y-93 .00002 pCi/1 Zr-95 .000003 pCi/1 Nb-95 .000004 pCi/1 Mo-99m .053 pCi/1 Tc-99m .0031 pCi/1 Te-127m .00002 pCi/1 Te-127 .00002 pCi/1 Te-129m .00015 pC1/1 Te-129 .00009 pCi/1 Te-131m .000009 pC1/1 Te-132 .00029 pCi/1 I-130 .00026 pCi/1 I-131 .76 'pci/1 1-132 .037 pCi/1 1-133 .11 pCi/1 1-134 .00038 pCi/1 i ' I-135 .012 pCi/1 Cs-134 .42 pci/1 Cs-136 .11 pCi/1 , Cs-137 .35 pCi/1 Cs-138 .002 pCi/1 Ba-140 .000015 pCi/1 1
$l ~ b
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i t TABLE 4.2-6 MAXIMUM CONCENTRATION INCREASES FOR DESIGN RELEASES (Con.'t) Environmental Medin Nuclide Concentration Increase (pC1/m2)
- ilim.n -40 yo;ir 15ul litup cr-Si .13 (Discharge Mn-54 .56 Canal) Fe-55 5.8 Fe-59 .057 Co-58 4.4 Co-60 12.
Rb-86 1.4 Rb-88 . .021 Sr-89 .11 Y-90 .032 Y-91m .00021 Y-91 180. Y-92 .00014 Y-93 .0069 Zr-95 .022 Nb-95 .013 Mo-99m 15. Tc-99m .077 Te-127m . 19 Te-127 .00067 Te-129m .5 Te-129 -
.00045 Te-131a .0011 Te-132 .094 I-130 .014 I-131 610.
I-132 .35 I-133 10. I-134 .0014 I-135 .34
.Cs-134 31000.
Cs-136 140. Cs-137 220,000. Cs-138 .0045 Ba-140 .019
+ 'lo m
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, 5.0 ADMINISTRATIVI: CONTROLS Objective To define the organization, assign responsibilitics, describe the environ-mental surveillance procedures, provide for a review and audit function, and prescribe the reporting requirements in order to insure continuinc protection of the environment and implement the Environmental Technical Specific ations .
5.1 ORGANIZATION The organization responsible for environmental protection, envi.ronmental monitoring and the implementation of the Environmental Technical Speci-fications, both prior to and following the issuance of an operating license for Crystal River Unit 3, is shown on Figure 5.1-1. 5.2 3ESPONSIBILITY The responsibility for the conduct of the preoperational environmental monitoring program described in Section 4 and special studies describea ' Gbum uo Ex uent rac in Section 6 is that of the hM- En;i ec6wf Department under the. Gaeiwam. *** Laws u., direction of the Director of C^^~""!c^ an d Pc;u!ater'; Affairs. Upon the issuance of an operating license the responsibility for the conduct of the postoperational environmental monitoring program and the imple-mentation of Environmental Technical Specifications becomes the re-sponsibility of the System Operations Department.
' -I -
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t SENIOR VICE PRESIDENT SYSTEM ENGIN E ERING & OPE R ATIONS m PO STO PE R ATIO N A L PREOPE R ATION AL m l' ' I
, VICE PRESIDENT ASSISTANT VICE PRESID E NT SYSTEM OPE R ATIONS QUALITY & ENVIRONMENTAL D E PART MENTS PRODUCTION DIRECTOR ENVIRONMENTAL & LICENSING SUPERIN TEN DENT AFFAI R S PRODUCTION SENERAL EN VIR O N ME NTA L STAFF PLANT SUPERINTENDENT NACLEAR PLANT S'_PERINTENDENT I
PLANT STAFF i Figure 5.l-l Organization for implementing Environmental Technical Specifications 5-2
4
- a. .
e The plart organization is responsible for the development of Operattnq ~ and Surveillance Procedures described generally in .'iection 5.5 and supplying ficld data to,the Production Environmental Staff as required by
- cetions 2, 4 .uul 6 of the 1:nvironmental Technical Specifications.
The Production Environmental Staff is responsible for consultant contracts, state and local regulatory agreements, assembly of '!ata preparation of repor s required by Section 5.6 of these Environmental Technical Spect-fications, and making recommendations to improve environmental pro-tection practices . o All reports and correspondence with the AEC regarding the Environmental Technical Specifications will be approved and signed by the ' ~ r'-' Vice President, System Operations . The Nuclear Plant Superintendent will, however, make reports by telephone and telegraph of any incic'ent or occurrence requiring reporting within 24 hours or less, as required in Section 5.6. e 5.3 REVIEW AN D AUDIT The FPC corporate Qualtiy Assurance organization under the direction of the Director of Quality Pagay"8 TAM
.- wh, has the responsibility of auditing the adequacy of the environmental monitoring and surveillance programs and auditing conformance to procedures and Environmental Technical Specification requirements . Figure 5.3-1 shows the reporting path for the Director of Quality _f_uMams
.._ m..~.Ja that is independent of the System Operations Department.
l
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l-e i SENIOR VICE PRESIDENT SYSTEM EN S1 N E E RIN G & OPER ATIONS y--- --- - 0 ASSISTANT VICE PRESIDE NT SYSTEM OPE R ATI ONS OE PARTM ENTS I l PRODUCTION DIRECTOR SUPERINTENDENT GUALITY - PROGRANS NUCLEAR SENERAL REVIEW COMMITTEE I PLANT REVIEW COM MITT EE LEGEND:
--- Q U A LIT Y ASSURANCE RE POR TIN G MANASEMENT RESPONSISILITY Figure 5.3-1 Organization for independent Review and Audit 5-5
4 r E. Review reported instances of violations of Environmental Technical Specifications and abnormal environmental occurrences. Where investi-cation indicates, evalu' ate and formulate recommendations to prevent recurrence .
- i. Review and compare the Safety Technical Specifications ar.d the Environmental Technical Specifications to avoid conflicts and maintain consistency.
fsN Tu t. uivi o.4 FOR ofEunod 5.4 ACTION TO BE TAKEN IF AKE i.EC:: .:E!!T1,1 P"CT"CT""
-CO'!D:~ C" IS EXCEEDED 5.4.1 Remedial actions as described in Section 2.0 of these technical specifications will be implemented until such time as the. liadir "$~~c.oaJ4..)
~ '21 f**.n.;Lario&,.,cn pr; EfE m _ is met.
5.4.2 The occurence shall be promptly reported to the Chairman of the Nuclear General Review Committee and investigated as specified in Section 5.3. 5.4.3 The Nuclear General Review Committee shall prepare. and submit "mmptly a report in writing to the * ~ ' "'-- n* Vice President, systnm Operations . The report shall describe the circumstances leadine to and resulting from the occurrence, and shall recommend appropriate action to prevent or reduce the probability of repetition.
- P' -' Vice President, System Operations . F 5all 5.4.4 The transmit a report of the occurrence to the ACC as specified in Section 5.6.2.
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( p 5.5 PROCEDURES bruar 5.5.1 D "^d written procedures, including applicable check-off lists and instructions, shall be prepared for the implementation of the monitoring requirements described in Sections 2 and 4, approved as specified in Section 5.5.2, and adhered to for operation of al'1 systems and components involved in carrying out the effluent release and environmental monitoring programs. Procedures shall include sampling, instrument calibration, . analysis, and action to be taken when limits are approached or exceeded. Calibration frequencies and standards for instruments used in performing the measurements shall be included. Testing frequency of alarms shall be included. These frequencies shall be determined from experience with similar instruments in similar environments and from manufacturers' technical manuals.
.( 5.5.2 All prccedures described in Section 5.5.1 above, and changes
'thereto, shall be reviewed as specified in Section 5.3 and approved by the Nuclear Plant Superintendent prior to implementation. Temporary changes' to procedures which do not change the intent of the original procedure may be made,,provided such changes are approved by two ::em-bers of the plant management staff, one of whom holds a senior operator's license. Such changes shall be documented, subsequently reviewed and approved by the Plant and Nuclear General Review Committees.
5.5.3 Prior to special tests or changes: A. If the Nuclear Plant Superintendent decides to make a change in the facility or Operating Procedures, or to conduct a test or experiment, and i~ concludes that the proposed change, test, or experiment does not involve i i i s
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[ f 5.6 PLANT REPORTING REOUIREMENTS 5.6.1 Routino Reports A semiannual Station Environmental Report covering the previous six
. months of operation shall be submitted to the Director of the Regional USAEC Regulaton Operations Office (cc to Director of Licensing) within 60 days after January 1 and July 1 of each year. The first such period shall begin with the date of initial criticality and terminate on January 1 or July 1, depending on the date of initial criticality. These reports shall include the following: .a A. The environmental surveillance data. The radiological environ- ., mental surveillance data will be summarized on a quarterly basis follow-ing the format of Table 5.6-1.
B. Analysis of the environmental surveillance data. This analysis will include discussion of any indications of radioactivity concentra-tions which are significantly higher than background levels. C. Records of changes in survey procedures. D. Records and results of Special Surveillance, Research, or Study Activities which are in progress or have been recently completed. E. Lng Co.a.idim. 6e, OrsumA Records of any occurrences in which ap r circ...crt:1 P::::: tion-Ca..Ja.. aas exceeded. I l -
,-9
.+.
f P. ' A summary of the quantitles.of radioactive effluents released from the plant as outlined in USAEC Regulatory Guide 1.21', with data summarized on a monthly basis following the format of Appendix " A" thereof. G. Records of changes as described in Section 5.6. 3.
. 5.6.2 Non-Routine Reports A. Radioactive Discharge
- If measured rates of release of radioactivity to the environment, averaged over a calendar quarter, exceed the design objective rates as specified in specifications 2.4.1.F for liquid effluents and in 2.4.2.G for air-borne effluents the Director of the Regional USAEC Regulatory Operations
.( Office (cc to Director of Licensing) will be notified within 30 days along a
with a report of the causes of the release rates and of a proposed pro-gram of action to reduce the release rates. B. Radiological Environmental Monitoring
- 1. If a single measured value of radioactivity oncentrations in critical pathway environmental medium samples identified in Section 4.2 exceeds a value equal to the preoperational background value as defined in Section 4.2 plus h-times the design objective maximum increase over background as defined in Section 4.2 then: (1) a study of ether available data and of repeat analyses to confirm or deny the validity of the high value will be made and the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) will be
! 10
( notified within one week of verification, (2) the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) will be notified of the results bf the study within two weeks of the completion
- of the study. . 2. If the average of the values of radioactivity concentrations in any critical pathway environmental media samples measured during a - calendar. quarter exceeds a value equal to the preoperational background value as defined in Section 4.2 plus e design objective maxi-mum increase over background as defined in Section 4.2 the Director of the Regional USAEC Regulatory Operations Office (cc to Director of Licensing) will be notified within 30 days of: (1) the measured values, (2) a study of other available data including plant discharge data to ascertain whether or not Crystal River Unit 3 operation is the source and (3) if the Crystal River Unit 3 operation is the source, of an appropriate i plant of action.
C. Nonradiological Discharges and Environmental Monitoring
- 1. In the event that a limiting condition for operation,is exceeded or an event involving a significant adverse environment impact occurs, a report will be made within 24 hours by telephone and telegraph to the Director of the Regional USAEC Regulator; Operations Office followed
" The telegraph report will quantify (59) by a written repogwithin : .
I the occurrence, its causes and, if aspects of the Crystal River Unit 3 operation are among the causes, planned remedial action to the extent possible. The written report w'll i fully describe the occurrence and will describe its causes and corrective action as fully as possible. L
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b cro w t w 4. w 3 9 3 .
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l t - c' 2. In the event that a reporting level specified in Section 4.1 is reached, a report will be made within 30 days to the Director of the Regional USAEC Regulatory Operations Office. . The report will describe: (1) efforts to confirm or deny the validity of - the observation, (2) efforts to determine the causes and whether aspects j of the Crystal River Unit 3 operation are among the causes and (3) planned action to prevent reoccurrences. 5.6.3 Chances . A. When a change in a plant design feature or operating practice as described in Section 3.0 or a procedure described in Section 5.5 is planned which, in the judgement of the applicant, would have a signifi-cant adverse effect on the environment or which involves an environ-
. mental matter or question not previously reviewed and evaluated by the l _
4 AEC, a report on the change will be made to the Deputy Director of Reactor Projects, Directorate of Licensing, USAEC (cc to Director of the , Regional Regulatory Operations Office) prior to implementation. The report will include a description snd evaluation of the change. gB Changes 1dditions to p its and certific 's required by Federal,
- Stat local or reg al authorities the protection o he environment will be orted. Whe e required cha is submitted to e con-corned agen for approval, ' will also be su tted to the Dep '
)
D . tor of Reac Projects, Di torate of Licensi USAEC (cc to 1 ( Directo the Regi Regulatory ations Office), f - nforma tion , j The submitta ' 11 inclu > n evaluation +he environmental act of ,, ! the change. hj - s
=,
5-13 i
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7 i computer run with parallel pararacters: (a) plant conditions (condenser flows, intake temperature, discharge temperature, loading, etc.) of all three units ,. (b) hydroldgical conditions (tidal stage, salinity traversos , etc. , (c) metcorological conditions (wet and dry bulb temperature, humidity, wind speed, wind direction, solar radiation, etc.) . The field survey measurements will be compared to the results of the computer-runs . Any modifications needed in either the physical model or the mathermatical model will then be incorporated in the models. The models will then be available to use in the evaluation of any abnormal environmental occurrence or other modifications in plant system or equipment performance. 6.3 INTAKE VELOCITY DETERMINATION ( Objective To measure the velocity of water at the intake screens and to verify the validity of the calculated value of intake velocity. General Approach and Schedule The intake velocity will be determined with appropriate instrumentation with an accuracy of.t0.1 fp6 during operation of all three units within a period of one year after startup of Unit 3. 6-:1
?
' RESPONSES TO AEC STAFF COMMENTS ON CR3 ETS NOT REQUIRING CHANGES TO ETS COMMENT NUPSERS (9.26) On page 75 of the July, August, September,1972 Florida Power Corporation Environmental ' Status Report, Dr. Fox states that no " Residual Chlorine"was detected just down stream of the Units 1 & 2 outfall. From the method cited " Total Residuah Chlorine" was actually measured. Sampling at the P.O.D. which is further downstream in the canal would result in no detectable concentrations.
(12) Regulatory (Safety) Guide 1.21, " Measuring and Reporting of Effluents from (57) Nuclear Power Plants" does not impose a limit on dissolved gases in liquid effluents. Florida Power is monitoring dissolved gases on a one batch / month basis to a sensitivity of 10' LF/ML as shown in Table 2.4-1 of the ETS. This is similar to other ETS's given to Florida Power by the staff as examples of acceptable monitoring programs. (16) The branching ratio is the ratio of two specified branching fractions of path-ways which a nuclide may decay. These fractions are well documented in the
" Table of Isotopes" resulting from studies by Lederer, Hollander, and Perlman, and which is used by the AEC in Regulatory Guide Development. Actually, we are measuring the end results of decay through gamma-isotopic analysis, and therefore, do not consider this question applicable to ETS. (ETS.
(Table 2.4-2 is from Reg. Guide 1.21). (17) Table 3.3-1 is already the maximum expected annual chemical use from the plant ' by interpolating or extrapolating the known amounts from Units 1&2.
f' . e (29) A well-balanced floral and faunal population does not depend on the presence of specific species. Measurements for determining such a population include productivity, respiration and biomass, and species diversity. The sampling, as designed, will measure the basis of the food web with a minimum of redun-doncy. It is a more meaningful indicator of condition than " gross species composition changes". Example Qs) In the summer of 1973, 13 samples were taken in the grassy portion of the discharge area. Biomass /m2 (gms, Dry Wt) was found to be 1.210.6. Should the mean fall outside this range, we would report it. (31) As stated, samples will be used to detemine species diversity. Species diversity is low when subject to strong "physiochemical limiting factors
-N and high in biologically controlled ecosystems", only the analysis of the data requires technically trained personnel. Changes in diversity are most
- evident and meaningful when the environment is in its most stable states winter and sumer.
*0dum, Eugene P.1971. Fundamentals of Ecology, 3 ed. W.B. Saunders Company, Philadelphia p.148 (32) c.M et visual observation while not as sophisticated as some methods is quite infomative and can be accomplished by a non-specialist. Major macrophytes and their relative density have been rapidly mapped using this method.
Sampling again is directed to the organisms most directly affected by the ; plant's discharge. __ It should be noted that the macrophytes determine the fauna by providing it cover, substrate, and food. The fauna influence the flora to a lesser degree than physical characteristics such as water quality, soil (substrate). salinity and temperature. 1}}