ML19317G433
| ML19317G433 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1973 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| NUDOCS 8003130880 | |
| Download: ML19317G433 (72) | |
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t ENVIRONMENTAL TECHNICAL SPECIFICATIONS APPENDIX B
_TO OPERATING LICENSE NO.
F FOR THE i
CRYSTAL RIVER UNIT 3 FLORIDA POWER CORPORATION DOCKET No. 50-302 9
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8003130 ppg
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TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1.1 Frequency 1-1 1.2 Gross (8,y) . 1-1 1.3 Point of Discharge (POD) 1-1 1.4 AT Across the Condenser 1-1 1.5 Unit 3 Mixing Zone 1-1 1.6 Emergency Ne'ed for Power 1-1 1.7 Abnormal Power Operation 1-1 1.8 Known Radioactive Source 1-2 1.9 Intake Area 1-2 1.10 Discharge Area 1-2 1.11 Inner Bay 1-2 1.12 Outer Bay _ 1-2 2.0 LIMITING CONDITIONS FOR OPERATION
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2.1 Thermal 2-1 2.1."1 Maximum T Across the Condenser 2-1 2.1.2 Maximum Discharge Temperature 2-2 2.2 Hydraulic 2-3 2.3 Chemical 2-3 2.3.1 Biocides 2-3 2.3.2 Corrosion Inhibitors 2-4 2.3.3 Dissolved Solids 2-4 2.3.4 pH 2-4 2.3.5 Other Chemicals which Affect Water Quality 2-4 2.4 Radioactive Effluents 2-4 2.4.1 Liquid Waste Effluents 2-5 2.4.2 Gaseous Waste Effluents 2-10 2.4.3 Solid Waste Handling and Disposal 2-2o 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Nonradiological Surveillance 3-1
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11 TABLE OF CONTENTS (Cont'd)
Page No.
3.1.1 Thermal Plume Model Verification 3-2 3.1.2 Benthos in Discharge Area 3-3 3.1.3 Marsh Grass 3-4 3.1.4 Impingement on Intake Screens 3-4 3.1.5 General Ecological Survey 3-5 3.1.6 Chemical Industrial Waste Water Treatment System 3-6 3.2 Radiological Environmental Monitoring 3-6 3.2.1 Media Other than Milk, Green Leafy Vegetables or External Gamma Radiation 3-9 3.2.2 Milk and Green Leafy vegetables 3-10 3.2.3 External Radiation 3-10 4.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES C
4.1 Thermal Plume During Unit 3 Operation 4-4.2 Intake Velocity Determination 4-4.3 Study of Erosion in the Discharge System 4 5.0 ADMINISTRATIVE CONTROLS
- 5.1 Organization 5-1 5.2 Responsibility 5-1 5.3 Review and Audit 5-3 5.4 Action to Be Taken if a Limiting Condition for Operation is Exceeded 5-5 ,
5.5 Procedures 5-5 5.6 Plant Reporting Requirements 5-7 5.6.1 Routine Reports 5-7 l
5.6.2 Nonroutine Reports 5-8 5.6.3 Changes 5-11 5.7 Recorda Retention 5-12 5.8 Special Requirements 5-12 e
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,r LIST OF TABLES i
No. Page No.
2.4-1 Radioactive Liquid Sampling and Analysis 2-21 2.4-2 Radioactive Gaseous Waste Sampling and Analysis 2-23 2.4-3 PWR-Liquid Waste System: Location of Process and Effluent Monitors and Samples Required by Technical Specifications 2-25 2.4-4 PWR-Gaseous Wasta System: Location of
, Process and Effluent Monitors and Samples
- Required by Technical Specifications 2-26 2.4-5 Average Energy Per Disintegration 2-27 3.2-1 , Sunmaary of Preoperational Environmental Surveillance Results 1971-1974 3-11 3.2-2 General Pathwa~y Radiological Environmental Monitoring Program 3-19 3.2-3 Critical Pathway Radiological Environmental i- Monitoring Program 3-22 3.2-4 Sample Station Locations 3-23 3.2-5 Typical Minimum Detectable Concentrations 3-26 3.2-6 Maximum Concentration Increases for Design Releases 3-28 5.6-1 Reporting of Radioactivity in the
- Environs 5-9 E
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List of Figures No. .
Page No.
1.1-1 Point of Discharge 1-1(a) 1.1-2 Inner and Outer Bays 1-3 3.1-1 Settling Ponds and Test Well Locations 3-7 3.2-1 Environmental Media and Exposure Pathways 3-18 3.2-2 Off-Site Sample Station Locations 3-24 3.2-3 On-Site Sample Station Locations 3-25 5.1-1 organization for Implemerting Environmental Technical Specifications 5-2 5.3-1 Organization for Independent Review and Audit 5-4 5.8-1 Chemical-Industrial Waste Water Treatment System 5-13 8
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1.0 DEFINITIONS The following terms are defined for uniform interpretation of the Environ-mental Technical Specifications for Crystal River Uni 3.
1.1 Frequency - Terms used to specify frequency are defined as follows:
One per shift - three times per day, interval may vary 1 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 112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />.
Weekly - Not less than 48 times per year, interval may vary by i 3 days.
Monthly - Not less than 10 times per year, interval may vary by 115 days.
Quarterly - Not less than 4 times per year, interval may vary by i 30 days.
Semi-annually - Not less than 2 times per year, interval may vary by i 60 days. .
1.2 Cross (8.y) Analysis - Radioactivity measurements of gross beta or gross r
i beta in conjunction with gross gamma as defined in Regulatory Guide 1.21.
1.3 Point of Discharge (POD) - Th'e intersection of the discharge canal and the original bulkhead line as shown on Figure 1.1-1.
1.4 AT Acro;p the Cendenser - The average temperature difference between the inlet did outlet of Un:t 3 condeneer boxes.
1.5 Unit 3 Mixing Zone - The enclosed area of the discharge canal bounded 4
by the eastern end of the canal and the cable chase from Units' 1 and 2 crossing the canal.
1.6 Emergency Need for Power - shall mean any event causing authorized Federal officials to require or request that the Florida Power Corporation supply electricity to points within or without tho State or other emergencies declared by State, County, or Municipal authorities during which an uninterrupted supply of electric power is vital to public health and safety.
1.7 Abnormal Power-Operation - The operation of Crystal River Unit 3 beyond these technical specifications due to the Emergency Need for Power.
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1.8 Known Radioactive Source - A traceable calibration source capable of reproducible geometry. The source shall be referenced to the original monitor calibration which produced the applicable calibration curves.
1.9 Intake Area - The intake canal and all of the water area south of the north intake dike and within two miles of the wast tip of the south intake dike.
1.10 Discharge Area - The discharge canal and all of the water area north of the south discharge dike and within two miles of the north discharge dike. ,
1.11 Inner Bay - An area as shown in Figure 1.1 which is five feet or less in depth composed of a mixture of grassy bottoms, oyster associations, algal bottoms and areas of sand and mud.
1.12 Outer Bay - The outer basin as'shown in Figure 1.1-2 - in which the planktonic ecosystem becomes as important as the bottom ecosystems.
, 1.13 Channel Calibration - The adjustment, as necessary, of the channel output s such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The channel calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the channel functional test. Channel cali-bration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
1.14 Channel Check - The qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
1.15 Channel Functional Test - The injection of a simulated signal into the l channel as close to tha primary sensor as practicable to verify operability )
including alarm end/or trip functions.
1.lo Dose Equivalent I-131 - That concentration of I-131 (uci/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of l I-131, 1-132, I-133, I-134 and 1-135 actually present. The thyroid dose l
conversion factors used for this calculation shall bc hose listed in Table III of TID-14844. j 1
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2.0 LIMITING CONDITIONS FOR OPERATION 2.1 THERMAL Objective (General)
To limit thermal stress to the aquatic ecosystem and control effluent cooling water temperature within prescribed limits which are consistent with applicable Federal and State regulations ,in order to minimize adverse thermal effects.
J 2.1.1 Maximum AT Across condensers i
Objective To limit the maximum temperature rise across the cc denser during normal operation at all power levels.
Specification 7
The temperature rise across the condenser shall not exceed 17.5'F for 1 e a period of more than 3 consecutive hours or a maximum of 21*F unless V there is an emergency need for power as defined in Section 1.
Monitoring Requirement The condenser temperature rise shall be monitored by detectors (RTD's 0-200 i l'F) located in the condenser inlet and outlet water boxes. The detector signal will be monitored by the control room .
computer. The AT will be alarmed at 17.5'F and at 21*F maximum.
If the RTD's or computer are inoperative'during power operation
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above 80%, the condenser AT shall be determined every 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s-
+ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> utilizing local temperature indicators on each water box l.
(30-130 1 2*F).
. Bases l
When Unit 3.is operated at design capacity, the intake temperature should be elevated by a value AT-of 17.5'F. When any one shell of the two twin-shelled surface steam cordensers is inoperative for
' maintenance or other reasons, the AT uill rise. 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 uprooted from the Gulf of Mexico, requiring
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temporary shutdown of a circulator to clean grass and other debris which has accumulated at the intake structure or inside the con-denser water boxes. This will cause a temporary increase in the AT across the condenser. Because of these conditions the AT of 17.5'F may be exceeded for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period with 21*F specified as a maximum 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 macimum temperature of the condenser cooling water discharged from the plant to the environment during normal operation.
Specification The temperature of the condenser cooling water at the Point of Dis-charge shall not exceed 103*F for a period of more than 3 consecutive hours or a maximum of 106*F unless there is an emergency need for power as defined in Section 1.
Monitoring Requirement The temperature at the point of discharge shall be monitored once per hour during power operations of Unit 3 utilizing the automatic or 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 1 0.2%.
If this buoy is inoperative, temperatures from other buoys (upstream and downstream) in the discharge canalshall be monitored. Once per hour during power operacions of Unit 3.
When the data acquisition system is inoperative the temperature at the point of discharge shall be estimated using operating and physical data in conjunction with curves generated by an empirical analysis of the Crystal River discharge canal variables.
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- lie effluent temperature limits during normal operations have been
! established to assure that the affected area within the receiving waters is minimized. Due to conditions as specified in Section 2.1.1 Bases, the condenser cooling water temperature of 103*F at the point of discharge may be exceeded for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period with 106*F specified as a maximum limit. , ,
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2-3 2.2 HYDRAULIC Not applicable.
2.3 CHEMICQ Objective (General)
To ensure that all chemical releases from the plant are controlled and diluted so as not to adversely affect public health or the natural environment and which are consistent with applicable State and local regulations.
2.3.1 Biocides Obj ective To limit the amount and concentration of total residual chlorine in the discharge.
Specification The concentration of total residual chlorine shall not exceed 1.8 ppm in an individual conden.ser outlet water box. The frequency of chlorination shall not exceed 30 minutes per water box per shift and chlorination of each of the condenser circulating pipes and water boxes shall be staggered to prevent simultaneous treatment with chlorine.
Monitoring Requirement A continuous chlorine recorder with a' detection limit of 0.1 mg/ liter shall be observed once each day on days when chlorination is performed to verify that the total residual chlorine does not exceed 1.8 ppm in the 1.9 er idual condenser outlet water boxes. The continuous chlorine anal;ter shall be calibrated semi-annually.
When the chlorine analyzer and/or recorder ere inoperative, a sample shall be taken of each affected water box weekly (during chlorination) and analyzed.
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. Only one of the four water boxes is chlorinated at a time. This results in water having a iaxinum chlorine residual of 1.8 ppm mixing with three equal volumes c f aater having a ninimum chlorine demand of 0.6 and the almost immadiate chemical reduction of the remaining chlorine within the Unit 3 discharge. As each L
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- e 2-4 water box is being chlorinated, a sample is taken from the outlet water box, analyzed for residual chlorine (free and combined), and the results are recorded on a circular recorder. 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 water box.
2.3.2 . corrosion Inhibitors No chromates shall be used.
2.3.3 Other chemicals which Affect Water Quality Chemical releases anticipated from the plant with the exception of chlorine-treatment of' the condenser cooling water are monitored as described in Section 3.1.6.
2.4 RADIOACTIVE EFFLUENTS Obj ective: To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as practicabic. These releases should not result in radiation exposures in unrestricted areas grer er than a few percent of natural background exposures. The concentration of effluent discharges of radioactivities shall be within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioactive material above back-ground to unrestricted areas be as low as practicable, the following design objectives apply:
For liquid wastes:
A. The annual dose above background to the total body or any organ of an individual from all reactors at a site should not exceed 5 mrem in en unrestricted area.
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B. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, discharged from each reactor should not exceed 5 Ci.
For. gaseous waste:
C. The annual total quantity of noble gases above background dis-charged from the site should result in an air dose due to gamma radiation of less than 10 mrad, and air dose due to beta radiation
. of less than 20 mrad, at any location near ground level which could' be occupied by individuals at or beyond the boundary of the site, and that no individual in an unrestricted area will receive an annual dose to the total body greater than 5 mrem or an annual skin dose greater than 15 mram from this release quantity.
D. The annual total quantity of all radiciodines and radioactive material in particulate forms above background from all reactors at a site should not result in an annual dose to any organ of an individual in an unrestricted area. from all pathways of exposure in excess of 15 mrem.
E. The annual total quantity of iodine-131 discharged from each reactor at a site should not exceed 1 C1.
2.4.1 Liquid Waste Effluents Specification A. The instantaneous concentration of radioactive materials released in liquid waste effluents from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.
B. The cumulative release of radioactive materials in liquid waste i
effluents excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
l C. The cumulative release of radioactive materials in liquid waste effluents excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
D. During release of radioactive vastes, the effluent control monitor shall be set to alarm and to initiate the automatic closure of l
each waste isolation valve prior to exceeding the limits specified in 2.4.1.A above. .
E. The operability of each automatic isolation valve in the liquid radwaste discharge lines shall be domonstrated quarterly.
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h t u e 2-6 F. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to t heir discharge when the projected cumulative release could exceed 1.25 Ci/ reactor /
calendar quarter, excluding tritium and dissolved gases.
G. The maximum radioactivity to be ccr.tained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 C1, excluding tritium and dissolved gases.
H. If the cumulative release of radioactive materials in liquid effluents excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall maSe an investigation to inentify the causes for such releases, define and initiate a program of action to reduce such re-leases to the design objective levels listed in Section 2.4, and a report of these actions shall be made to the USNRC in accordance with Section 5.6.2.B(1) .
Liquid Waste Sampling and Monitoring Requirements t
I. Plant records shall be maintained of the radioactive conhentration and volume before dilution of liquid waste
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intended for discharge and the average dilution flow and length of time over which each discharge occurred. Sample analysia results and other reports shall be submitted in accordance with Sectich 5.6.1.B. Estimates of the sampling and analytical errors associated with each reported value shall be included.
J. Prior to release of each batch of liquid waste, a sample shall be taken from that batch and analyzed for the con-centration of each significant gamma emitting isotope in accordance with Table 2.4-1 to demonstrate compliance with Specification 2.4.1 using the ficw rate into which the waste is discharged during the period of discharge.
l K. Sampling and analysis of liquid radioactive naste shall be performed in accordance with Table 2.4-1. Prior to taking samples from a monitoring tank, at least two tank i
volumes shall be recirculated.
l L. The radioactivity in liquid wastes shall be continuously monitored and recorded during release. Whenever these ,
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2-7 monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be ana-lyzed and two plant personnel shall independently check valving prior to the discharge. If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a liquid waste tank shall be made and any release in progress shall be terminated.
M. The flow rate of liquid radioactive waste shall be continuously measured and recorded during release.
N. All liquid effluent radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Standards source. The relationship between effluent concentration and monitor readings should be established.
Each monitor shall also have a functional test monthly and an instru-ment check prior to making a release.
O. The radioactivity in low power generator bleeds shall be sampled upon commencement of bleeds and every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereaf ter and analyzed for gross radioactivity concentration. Low power generator bleed with radioactivity levels in excess of Specification 2.4.1.A will be directed to the liquid radwaste system for further processing.
P. The points of release to the environment shall be monitored in accordance with Table 2.4-3.
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Bases The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual dose to the total body or any organ of an individut.1 in an unrestricted area vill not exceed 5 mrem. At the same time, these specifications permit the flexibility of operation, compatible with con-siderations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20. It is
[ expected that by using this operational flexibi ity under unusual operating I
conditicas, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.
i l The design objectives have been developed based on operating experience l
taking into account a combination of variables including defective fuel,
- primary system leakage, primary to secondary s-stem leakage, and performance of the various waste treatment systems. ,
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2-8 A. Specification 2.4.1.A requires the licensee to limit the concentration of radioactive materials in liquid waste affluents released from the site to levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for un-restricted areas. This specification provides assurance that'no member of the general public will be exposed to liquid containing radioactive materials in excess of limits
, considered oermissible under the Commission's Regulations.
- 5. Specification 2.4.1.B and 2.4.1.C establish the upper limits for the release of radioactive materials in liquid effluents. The intent of these Specifications is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under i
unusual operating conditions which may temporarily
- result in releases higher than the levels normally achievable i
when the plant and the liquid waste treatment systems are functioning as designed. Releases of up to these levels will result in concentrations of radioactive material in liquid waste effluents at small percentages of the limits specified in 10 CFR Part 20.
C. Specifications 2.4*l.b and 2.4.1.E require that suitable equipment to control and monitor the releases of radioactive materials in liquid wastes are operating during any period these releases are taking place consistent with the require-ments of 10 CFR Part 50, Appendix A, Design Criterion 64.
D. Specification 2.4.1.F requires that the licensee maintain and operate the equipment install &d in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the. requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable. assurance that the quantity released will not exceed the design objective. In order to keep releases of radioactive materials as low as
- practicable, the specification requires' operation of
- equipment whenever it appears that the projected cumulative I discharge rate will exceed one-fourth of this design ob-( jective annual quantity during any calendar quarter.
l e
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m
,s ,.
, 2-9 -
E. . Specification 2.4.1. G limits the amount of radioactive material that could be inadvertently released to the environment to an amount that will not exceed the Technical Specification limit.
F. In addition to limiting conditions for operation listed under Specification 2.4.1.B and 2.4.1.C, the reporting requirements of Specification 2.4.1.H delineate that the licensee shall identify the cause whenever the cumu-lative release of radioactive materials in liquid waste effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design objective levels on timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred.
G. The sampling and monitoring requirements provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the require-ments of Design Criteria 60 an 64. These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 4.6.1.B in conformance with Regulatory Guide 1.21. On the basis of such reports and any additional information the Commission may from time to time require the licensee to take such action as the Commission deems a.propriate. .
,e
' ~
.. 2-10 ,.
2.4.2 Caseous Waste Effluents .
Specification The terms used in these Specifications are as follows:
subscripts v, refers to vent releases i, refers to individual noble gas nuclide (Refer to Table 2.4-5 for the noble gas nuclides considered) .
Q = the total noble gase release rate (Ci/sec)
T giQ s'um of the individual noble gase radionuclides determined to be present by isotopic analysis li= the average total body dose factor due to gamma emission (rem /yr per Ci/sec)
II= the average skin dose factor due to beta emissions (rem /yr per Ci/sec) 5 = the average air dose factor due to beta emissions (rad /yr per Ci/sec)
II = the average air dose factor due to gamma emissions (rad /yr per Ci/sec)
The values of K, L, 5 and II are to be determined each time isotopic analysis is required as delineated in Specification 2.4.'2.7 Determine the following using the results of the noble gas radionuclide analysis:
K IE=(1/QT)fQii II = (1/QT) 1[Qil i M = (1/QT) 9M1i T N II = (1/Q ) f91 i where the values of Kg, Li , Mi and Ni are provided in Table 2.4-5, l ' and are site dependent gamma and beta dose factors
- O e
G
ru *
~*---.... . _
~
~
Q = the measured release rate of the radiciodines and radioactive materials in particulate forms with half-lives greater than eight days. (,Ci/,44c.) -
- 4. (1) The release rate limit of noble gases from the site shall be such that 2.0 QgEy 11 and
- 9 0.33 QTv(L v + 11 1*Dv )[
(2) The release rate limit of all radioiodines and radi.3 active materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous vastes from the site shall'be such that 3.3 x 10 Q y 11
- 6. (1) The averaEe release rate of noble gases from the site during any calendar quarter shall be such that 13 Qg _N 11 and 6.3 Q3 II, 11 (2) The average release rate of nobic gases from the site during any 12 consecutive months shall be 25 Q II 11
. Tv v ,,
and 13 Qgy M 11 T mra
.' 3.
~- 5
. . . _ . . . . -- . 2-12 '
l
. (3) The average release rate per site of all radioiodines and radio-active materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that 7
13 35x10 Q, .11 (4) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be such that 25 3 3 x10 Q, _
.11 (5) The amount of iodine-131 released during any calendar quarter
~
shall not exceed 2 Ci/ reactor.
(6) The amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 Ci/ reactor.
C. should any of the conditions of 2.4.2.c(1), (2) or (3) listed below exist, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective icvels listed in Section 2.4 and report these actions to the NRC within 30 days from the end of the quarter during which the releases occurred.
(1) If the average release rate of noble gases from the site during any calendar quarter is such that l
50 Qyy >l l or 25 >1 Q.hHv .
l
~, . . . . ... . -. . .. "-
2-13 -
. ~
(2) If the average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter is such that 50 3.3 x10 Q, >1
.\ .
(3) If the amount of iodine-131 released during any calendar quarter is. greater than 0.5 Ci/ reactor.
D. During the release of gaseous wastes from the primary system vaste gas holdup system the effluent monitor for the Waste Gas Storage Tanks shall be operated and set to alarm and to initiate the automatically closure of the waste gas discharge valve prior to exceeding the limits specified in 2.4.2.A above. The operability of each astomatic isolution valve listed in Table 2.4 ~
shall be demonstrated quarterly.
I EE . The maximum activity to be contained in one waste gas storage j tank shall.not exceed 47,000 curies ,(considered as Xe-133). l 1
Caseous Waste Samoline and Mosit6rins'Recuirements
. F. Plant records shall be maintained and reports of the sampling and analyses results shall be submitted in accordance with Section5.6ofthese5pecifications. Estimates of the sampling and analytical error associated with each reported value should be included. 1 1
l
e s e f' .
Q. Caseous releases to the environment (noble gases), except from the turbine building ventilation exhaust shall be continuously monitored and recorded for gross radioactivity and the flow continuously measured and recorded. Whenever these monitors are inoperable, grab samples shall be taken and* analyzed daily for gross radioactivity. If these monitors and/or recorders are inoperable for more than seven days, these releases shall be terminated.
H. Durins the release of saseous wastes from the Primary system vaste gre holdup system, the gross activity monitor, the iodine
~
collection' device, and the particulate collection device shall be operating. .
][. All waste gas effluent monitors shall be calibrated at least quarterly by means of a known radioactive source which has been calibrated to a National Bureau of Standards source. The relation-ship between effluent concentration and monitor readings should be established. Each monitor shall have a functional test at least monthly and instrument check at least daily.
Cf.
Sampling and analysis of radioactive material in gaseous waste, l
)
including particulate forms and radioiodines sha'll be performed in accordance with Table 2.4-2.
K. The points of release to the environment hballbemonitoredin ~
accordance with Table 2.4-4.
I
x
<* 2-15 . c.. i v: -
.. _ y ,
.*l ~
. Bases: The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 26 and should be as low as practical in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual air dose from the site due to gamma radiation will'not exceed 10 mrad, and an annual air dose from the site due to beta radiation will not exceed 20 mrad from noble gases, that no individual in an unrestricted area vill receive an annual-dose to the total body greater than 5 mrem or an annual skin dose greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual from radiciodines and radioactive material in particulate form with half-lives greater than eight days will not exceed 15 mrem per site.
~
At the same time these spe_ifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may temporarily rcault in releases higher than the design objective icvels but still within the concentration limits spe.cified in 10 CFR Part 20. Even with this
. operational flexibility under unusual operating conditions, if the licensee exerts every effort to keep levels of rzdioactive material in gaseous vaste effluents as lov as. practicable, the annual releases vill not exceed a small fraction of the concentration limits specifi,cd
~ '
- in 10 CFR Part 20. ,
5 e-J
,.=O 2-16 '.'
The design objectives have been developed based on operating experience taking into account a ecmbination of system variables including defective fuel, primary system leakage, primary to secondary sys' tem leakage, and the performance of the various waste treatment systems. .-
Specification 2.4.2./U(0 limits the release rate of noble gases from the site. so that the corresponding annual gamma and beta dose rate above background to an individual in an unrestricted area will not exceed 500 mrem to the total body or 3000 mrem to the skin in compliance with the limits of 10 CFR Part 20.
l' For Specification 2.4.2. A(t), gamma and beta dose factors for the individual noble gas radionuclides have been calculated for the plant gaseous release points and are provided in Table 2.4-5. The expressions used to calculate these dose factors are based on dose models derived in Section 7 of Meteorology and Atomic Energy-1968 and model techniques provided in Draft Regulatory Guide 1.AA.
Dose calculations have been mad ~e 'to determine the site boundary location with the highest anticipated dose rate from nobic gases using on-site meteo'ological r datia and the dose expressions provided in Draft l Regulatory Guide 1.AA. The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclides. ,
l 1
l
._w
- t. 2-17 .
r
. 7 The offsite location with the highest anticipated annual dose from .
released noble gases is 145'o meters in the ENE direction.
The release rate Specifications for a radioiodine and radioactive material in particulate form with half-lives greater than eight days are dependent on existing radionuclide pathways to man. The pathways which were examined for these Specifications are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consnmption by man, and 3) deposition onto grassy areas where milch animals graze with consumption of the milk by man. Methods for estimating doses to the thyroid via these pathwcys are E described in Draft Regulatory Guide 1.AA. The offsite location with the highest anticipated thyroid dose rate from radiciodines and radioactive material in particulate form with half-lives greater than eight days was determined using on-site meteorologien1 data and the expressions described in Draft Regulatory Guide 1.AA.
Specification 2.4.2.A(2) limits the release rate of radioiodines and radioactive material in particulate form with half-lives greater than eight days so that the corresponding annual thyroid dose via the most restrictive pathuay is less than 1500 mrem.
For radioiodines and radioactive material in particulate form with half-lives greater than eight days, the moc: restrictive location is a Wi[ Acou 3 located M00 meters in the EpJE. direction ;
U 3 (vent E/Q =l.78x 10 sec/m;), ,
l i
e
,, 2-18 ,.
Specification 2.4,2,8 establishes upper offsite levels for the releasea of nobic gases and radioiodines and radioactive material in particulate form with half-lives greater than eight days at twice the design objective annual quantity during any calendar quarter, or four times the design objective annual quantity during any period of 12 consecutive months.
In addition to the limiting conditions for vperation of Specifications 2.4,2.A and 2.4.1.B. the reporting requirements of 2.4.2.C provide that the cause shall be identified whenever the release .f gaseous effluents exceeds one-half the design objective annual quantity during any calendar quarter and that the proposed program of action to reduce such release rates to the design objectives shall be described.
Specification 2.4.2.D requires that suitable equipment to monitor and control the radioactive ~ gaseous releases are operating duiing any period these releases are taking place.
Specification 2.4.2.E limits the maximum quantity of radioactive gas that can be contained in a vaste gas storage tank. The calculation of this quantity should assume instantaneous ground release, a X/Q based on 5 percent meteorology, the average gross energy is 0.19 Mev per disintegration (considering Xe-133 to be the prir.cipal emitter) and exposure occurring at the minimum site boundary radius using a semi-infinite cloud model. The calculated quantity vill limit the offsite dose above background to 0.5 rem or less, consistent with Commission guidelines.
o 1
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}
" 2-19
(
, -]i The sampling and monitoring requirements given under Specification ~',
2.4.2, provide assurance that radioactive matsrials released in -
gaseous waste effluents are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive waste effluents released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
The points of release to the environment to be monitored in Section 2.4.2 include all the moritored release points as provided for in Table 2.4-4.
Specification 2.4 2.4 cxcludes monitoring the turbine building ventilation exhaust since this release is expected to be a negligibic release point. Ifany PWR reactors do not have turbine building enclosures.
~
To be consistent in this requirement for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required.
l 4
se 2- 2.o .
2.4.3 Solid Waste Handling and Disposal Specification A. Measurements shall be made to determine or estimate the total curie quantity and principle radionuclide composition of all radioactive solid waste shipped offsite.
B. Reports of the radioactive solid waste shipments, volumes, principle radionuclides, and total curie quantity, shall be submitted in accordance with Section 5.,6.1.
Bases The requirements for solid radioactive waste handling and disposal given under Specification 2.4.3 provide assurance that solid radioactive materials stored at the plant and shipped offsite are packaged in conformance with 10 CFR Part 71, and 49 CFR Parts 170-178.
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9 m
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- a Tnbic 2.4-1 .
- f
.R.@).0,A,g,1,VA,1J,qll,TD.RA!1Pl.T,N,C, AMD, A!!,ALYS,T,5 .i 1.Iquid Snmpilny, Type ul Uttectallo Soure.c Frequency Activity Annlynin CunesntralIgan *
. . ._ __ _ __.._ _ . _ . . __ _ _ .. _ . ._.. ___ _ ___ _ . . ._L '!!!!.= 0D A. Monitor Tank. Rolcanes , Cach nntch (Crab samoleil'rj ncipal Cat.una Emi tters 5 x 10 -7 (2)
(Grab
- One Batch / Month n.nla Disr.olved Canen(5) 10" 4
- Weekly Composite (1) -6 Ha-1.a-110. 1-131 10
+ Monthly Composite (1)* H-3 10
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~ '
From Grab Samples) Cror:r. n 10 I
-8 Monthly Corepost to(1) Sr-90 5 x 10
~
- B. Prir.ary coolant Weekly (N 1-131. 1-133 -
10 C. Low Power Cencrator Bleeds Commencemer.t of -- ---" 7.nw enanah to be belov
. Bleed (Grab Sample) Gross p 10 CFR 20 limits
! . Every 4_ hrs durina Bleed Gross _B Low enniah to be below **
. 10 CFR 20 limits 1
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/ .
Table 2.4-1 (continued)
.W.[S_ t
.) A com'posite c$mple is one in which the quantity of liquid sampled is proportional to the quantity of liquid vaste discharged.
i
') For certain uintures of gn==a emitters, it may not be possible to '
mensure radionuclides in concentrations near their sensitivity ,
limits when other nuclides are present in the sa=ple in =uch greater concentrations. Under these circumstances, it will be = ore appro- .
priate to calculate the concentrations of such radionuclides using measured ratios with those radiocuclides which are routinely identified and measured. .
) The detectability licies for cetivity analysis are based on the technical feasibility and on the potential significance in the -
environ =ent of the quantities released. For so=e nuclides, lower ,
detection limits may be readily achievable and when nuclides are ~
measured below the stated limits, they should also be reported.
)
The power level and cleanup or purification flow rate at the sa ple
. time shall also be reported. ,
) For dissolved noble gases in water, assume a MPC of 4 x 10~5 p Ci/ml of water. '
9 O
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s Tchic 2.4-2 .
. RADI0 ACTIVE CASEOUS UASTE S/J9 LING AMD /J:ALYSTS FREQUENCY
~
Caccous Snepling and Analysis Type of D7tcctahic
, Scurce Frequency Activity Analysin
~
Concentratgs
__0G/nO.
10" (}
A. *deste Ces Decay Each Tank (Crab Sample) Prinef pal Carm E:::itters ,'
Tank 1cler.scs Release .
~0
'H-3 10
~
Containment Purgo Releases Each Purge - Principal Camma Emitters 10 B.
- (Grab Sanple) _
-6 10 (}I)
C. Condenser' ir Ejector Weekly (Grab Sample) Principal Camma Emitters
." Hontly (Grab' Sample) H-3 ' 10~
~ '
Weekly (Gas Grab Sample') Principal Cammt. Emitters 10 ) (3)
D. Environmental Release Points Montly_(Cas Grab Sample) 11 - 3 10' On Line RMS) -12 Weekly ((Charcoal Filter) I-131 10
' - , (On Line RMS) 10
-10 Monthly (Charcoal Firer) I-13 , I-135 (On Line 10!S) .
Weckly (Particulate Filter) Principal Cam:na Emitters ,g to Ga-La-ll0. 4 T-111 nna n%r.)
Monthly Composite *
> ', . (Particulate Filters) 10
_g .
Cross a
' 8, ~
1 .
Quarterly Composite () 8[
3 9 10 (Particulate Filters)
~ -
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, , 2-24 4 e-Table 2.4-2 (Continued) .
2:0TES: -
(1) The above detectability limits for activity analysis are based on technical frasibility and on the potential significance it the
. environ =ent of the quantities released. For some nuclides, lover detection licits may be readily achievable and uhen nuclides are maacured below the stated limits, they should also be reported. ~
(2) Analyses shall also be perfor=ed following each refueling, startup" or similar operational occurrence which could alter the ~irture of .
radionuclides. . .
(3) For certain =ixtures of'ga==a coitters, it ray not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are'present in the sacple at much higher levels.
Under these circu= stances, it will be core appropriate to calculate the levels of such radionuclides using observed ratios *-ith thosa ,
radionuclides which are measurable.
(4) To be representative of the average quantitics and concen:ratior.s of radioactive caterials in particulate form released in gmous effluents, sa:ples should be collected in propertion to the rate of flew of the effluent stream. --
~~
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': ... 2 ..
l .
T-
r-----_______,
F 4
Table 2.4-3 PWR-LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLES REQUIRED BY TECHNICAL SPECIFICATIONS Grab High Liquid Radiation Auto Control to Continuous Sample Cross Dissolved Isotopic Level
'roeve Stream or Release Point Alarm Isolation Valve Monitor Station Activity I ' Cases Alpha H-3 Analysis Alarm
!vrpsrator Condensate Storage X X X X X X X
.tnks (A & B)
Aundry & Shower Sump Tank
- X X X X X x g
'ricory Coolant System X X
.iquid Radwaste Discharge X I X X X
'ip2 lutdmer Storage Tanks X X -
pstantially radicactive)
- ondsnsate Stor.,ge Tanke & X X X** X iccondary Neutra?izer Tank kaponent Cooling Systems X I X *
.urbine Building Sumps
- Floce Drains)
X X Xae . I fuelasr Service Area Sump ., X X Xaa
~
- In most FWR's the contents of the detergent waste collectorhtank are sampled, analyzed and then filetered prior to release through the liquid radvaste discharge pipe. The' detergent waste system should be designed with either a aplit tank or ,two separate collection or sample (rest)' tanks to permit isolation of the tanks for mixing, sampling and opslysis prior to release.
8 1ib analysis capability i
\
=
Tetle 2.4-4
- FWR-CASF0tJS VASTE SYSTCM
\ ibCATT0ff Of TROCF.SS AltD EFFf.tfDef MOM 810M5 A#O 5 AMrl.tus RErMf 9FD BY Tf!OMf frat. SPECIFICATrosts .
Crab Radiation Auto Centrol to Continuove sample Pesvarenc3 Frecete Streng er Relente Fetat Alarm Tnelstten Valve _Han_t ror_ Station WC _ 1 Part M g
=
Veste Cao Storese Yanks X X X X X X X X X
- 3 CondeAer Atr Removal System ,, X' X ,X X X X X t
- Tent Reader Systen* X X X X X X X X Buildtog Ventilation Systees .
Reactor Contair.nent Building (whomever .
, there le flow) - X X . F X X X X X X Aunt 11ery Butiding* X X X X { X X X X Y M
T sel Itandling & Storage Building
- X X X X X 'M *X X *
. Radweste tuttdtng* X X X X X X X X
- 1f any or all of the procese streams or building ventilation syntcom are rested to a sint.1e release point, the need for a conttavevo monitor at 8 g *h
. Itw inJ!vidual discharr.o retnt to the main exhaunt duct te ellutanted. One continuova semiter et the flant retenac point in soffletent.
. e .
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Table 2.4-5 Y#
GAMMA AND BETA-DOSE FACTORS FOR Crystal River Unit 3 .
x/Q = 1.46 x 10-6 ,,ef,3 at 1450 meters, ENE ,
Dose Factors for Vent Nable Gas Kiy L.y Miy Niy Radionuclide Total Body Skin Beta Air Gamma Air
( rem /yr } rad /yr rad /yr
\ Ci/sec / {Ci/sec/ren/yrj 1 C1/sec)/ (Ci/sec} /
~
~
Kr- 83m 7.0 x 10 0 0.92 '0.035' g i
Kr-85m 0.80 2.1 2.9 0.84 4
\ N
. 96 2.0 2.8 I 0.010 Kr-85 .
Kr-87 2.5 14 15 2.6 Kr-88 6.1 3.5 4.3 6.4 '
Kr-89 2.79 15 15 0.83
. Xe-131m 2.28 0.69 1.6 0.35 -
Xe-133m 0.22 1.'5 2. 2 - 0.29 Xe-133 0.26 0.55 1.5 0.31 Xe-135m ,
1.2 1.0 1.1 1.1
~
Xe-135 1.2 2.7 3.6 1.3
, Xe-137 0.12 18 . 19 0.12 Xe-138 2.4 6.0 6.9 2.5 . . I ;
, FA =
y, n e-e . 3-1
- 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 NONRADIOLOGICAL SURVEILLANCE Study Plan The estuary has been exposed to the influence of the operation of Units 1 and 2 for approximately seven (?) years. During this time, the systems in the area have adapted to this influence. A pre-operational surveillance program was designed to determine the exact nature of the new stabilized conditions relative to control areas adjacent to the plant site. This surveillance consisted of system modeling with measurements of biomass, productivity, respiration and diversity in all major compartments. The information derived will serve as a baseline for comparison with the data taken after Unit 3 becomes operational.
The post-operation surveillance program is designed to determine any significant environmental effects of the operation of the power plant, particulary unpredicted and catastrophic changes. The program consists of 4 short-term intensive surveillance program elements and 2 long-term program elements.
A period of adjustment of the ecosystem is expected concurrent with Crystal River Unit 3's initial operation. This will be a localized perturbation limited to a portion of the inner bay associated with the higher water velocity as well as the temperature increase re-sulting from the condenser discharge.
Any ecosystem which experiences a change in its environment will-undergo a period of adaption unless catastrophic conditions occur.
With the small changes anticipated with the addition of Unit 3, no catastrophic effects are expected. However, any changes in the en-vironmental 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 ?9ttwuties I
l* r-Time to Miiiisa m l t { Apprer.irnate Time to S:siliutica i I l
8 I l - Stab;iial Lei i
1 I
Produ.ti.ity ' -
-- _ - - --- -- Initial tawl i
- ' _ _ _ _ - - - - - .- - - Minimum Lawl 9
Time *- ,
Mb w
s., , - -
9 .-
F-F2 In this pacticular system the final stab 11 zed level is higher than the initial level and is only obtained after a period of stablization and after going through a suppressed level following the initial per-turbation. The recognition of this type of potential response is obviously important in considering any surveillance program.
The models of the systems 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 in-tensive surveillance program elements allows one year of monitoring to determine the transient response that the systems are experienc'ing.
An additional year of monitoring is required to indicate the new stabilized level. If the second year's data indicate that the systems have not approached stabilization, the monitoring will be extended for an additional year. It is anticipated that the intensive surveillance program elements should not be necessary beyond three years.
The areas in which intensive monitoring vill be performed as indicated or until stabilization occurs include the following program elements:
(1) Thermal plume model verification, (2) Benthos in discharge area, (3) Marsh grasses, and (4) Impingement on intake screens.
In addition to the s ort-term intensive surveillance program elements designed to determine how the systems hav.e responded to the per-turbations, an on-going program element designed to obtain a diagnositic view of the condition of the environment will be continued during the operational life of the plant. This indicator program element consists i of a number of simple measurements which will detect any major changes in the system. A second long-term program element involves chemical-industrial waste water monitoring.
l 3.1.1 Thermal Plume Model Verifidation Objective To verify previous calculations which predict the size and location of the effluent thermal plume.
Specification Salinity, temperature, and depth measurements shall be made in the discharge area under varying tidal conditions. Isothermal contours shall be mapped and compared with predicted values. Two surveys shall be made during the first year of operation: one with winter conditions and one with summer conditions.
1 1
s 5 .-
3-3 -
Reporting Requirement Results of the data gathered in this program elementshall be reported in accordance with Section 5.6.1. In addition, any isotherm which exceeds the predicted area by 30 percent shall 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 4 30 percent was established because this is the maximum expected error of the analytical' program due uncertainties caused by solar back-radiation.
3.1.2 Benthos in Discharge Area Objective To determine the ecological condition of the benthic system in the area directly affected by the thermal plume.
Specification Post-operational monitoring of productivity, respiration, diversity and biomass of the benthic system in the area adjacent to and north of the discharge canal shall be measured on a quarterly basis until the system has approached stabilization. Samples shall be taken by harvesting quadrats, by sediment cores, and by venturi pumps. The number, frequency and location of samples to be taken shall be determined from a statistical analysis of the research presently being conducted in this area. Samples i
shall be stratified by macrophyte dominance. Productivity and respiration of the syste a shallbe determined by the methods currently employed in the modeling work.
Reporting Requirement Results of the data gathered in this program element snall be reported in accordance with Section 5.6.1. In the event that any parameter measured changes beyond two standard deviations of*the value measured in the preoperational monitoring program a report shall be submitted as specified in Sectic; 5.6.2.
I Bases In the discharge area adjacent to the canal, the productivity, respiration j j and biomass should increase due to an increased temperature of the !
cooling water. If any of these parameters changes beyond 2r of that measured during preoperational monitoring, the system should be in- ,
vestigated for catastrophic results.
JO
's c 3-4 3.1.3 Marsh Grass Objective To determinn the ecological condition of the salt marsh adjacent to the discharge area.
Specification The biomass, productivity, and respiration of the salt marsh shall be measured on a qua<rterly basis after plant operation begins until the system has approached stabilization. Quadratsshall 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.
Reporting Requirement Results of the data gathered in this program element shall be reported in accordance with Section 5.6.1. In the event that any parameter measured changes beyond 20 of the value ceasured in the preoperational monitoring program a report shall be submitted as specified in
~
Section 5.6.2.
Bases The metabolism of the marsh grass is expected to increase with in-creasing temperature. Any decrease indicates a breakdown of structure.
If any of these parameters changes beyond 2c of that measured during preoperational monitoring. the system should be investigated for cat-astrophic results.
3.1.4 Impingement on Intake Screens Objective To determine the quantity of impinged fish on the intake screens to compare with preoperational data.
Specification-The' fish collected in the trash racks adjacent to the intake screens of Units 1 and 2 and Unit 3 vill be sampled for 24 consecutive hours once weekly. This program shall be conducted for one_ year after operation of Unit 3 begins. This program may be ,
terminated after one year period with staff's approval. Samnian shall be sorted according to species, length, and wet weight.
_. e -
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- 1 3-5 l Reporting Requirement Results of the data gathered in this program element shall be reported l in accordance with Section 5.6.1. Any daily sample with biomass greater than 50 kg shall be reported 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.
3.1.5 General Ecological Survey
,.- Objective To detect changes which might occur and would be uued to indicate areas requiring more detailed investigation.
Specifications
.F A series of measurements shallbe carried out during the operational k life of the plant to indicate the general condition of the environment.
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 9 zooplankton net shall be made semiannually. Species diversity will be determined.
- b. Canals. The percent of saturation of oxygen shall be measured at dusk and dawn twice monthly at the point of discharge.
- c. Intake screens'. The screen-wash racks shall be monitored visually daily to determine any abnormal catches.
- d. Inner bay. Quarterly tows by a man in a glass-bottomed boat to observe the general condition and percent cover of the grasses shall be made. These tows shall be along a transect along a radial from the plant.
- e. Oyster reefs. Counts of the species diversity within a
. quadrat on the reef shall be made quarterly.
- f. Marsh grasses. Stem counts of grass within a quadrat will be made' quarterly. This measurementshall be correlated with biomass.
In addition, the number of crab holes within a quadratshall be observed as a biomass indicator.
- r
.- 3-6 Reporting Requirement Results of the data gathered in this program element will be reported in accordance with Section 5.6.1.
Bases j The parameters to be measured were chosen to indicate general trends in the conditions of the environment and will be used to indicate areas where-further investigations may be warranted if significant changes are detected.
3.1.6 Chemical - Industrial Waste Water Treatment System Objective To monitor the Chemical-Industrial Waste Water Ponds, and surrounding environs.
Specification Representative samples shall 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. (See Figure 3.1-1) i Samples are analyzed for pH Nitrate (NO3 ), Sulfate (SO 4), Phosphate (P0g), Iron (Fe), dissolved solids, Copper (Cu), and Zine (Zn).
Reporting Requirements Reports shallbe furnished in accotlance with Section 5.6.1.
Basis -
Monitoring is performed to assure that all chemical industrial waste water is controlled so as to not adversely affect public health or the natural aquatic environment. .
3.2 ' RADIOLOGICAL ENVIRONMENTAL MONITORING Objective The radiological environmental monitorir.g program will provide information which can be used to assist in assessing the typc and quantity of radiation exposure in unrestricted arean resulting from plant operation.
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Background
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 pregram was operated by the University of Florida.
A summary of the preoperational surveillance results is shown in Table 3.2.1. This summary includes median val 6es of the observed ,
environmental concentrations and 95 percentile values (i.e., values -
which exceed 95 percent 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 operation of the plant operation contributes neg-ligibly 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 con-centrations.
r Specification (Program)
Environmental media which are sampled and .nalyzed for radioactivity are shown by the two diagrams on Figure 3.2.-l. Each oox in the dia-grams 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.
The operational radiological monitoring program shall consist of a continuation of the preoperational program of measurements of radio-activity in environmental media which is outlined in Table 3.2-2.
The critical pathway monitoring program which is included in Table 3.2-2 is also shown in Table 3.2-3. Sample station locations are described on Table 3.2-4 and shown on maps on Figures 3.2-2 and 3.2-3 Typical minimum detectable concentration values are given on Table 3.2-5.
Table 3 .2-6 presents the ancicipated 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 increases from the plant's release of I-131 should be less than 15 mrem /yr. All of.the values listed in Table 3.2-6 were derived from 5
- 9
ne
~
1 3-9 the design release values listed in the " Final Environmental State-ment" (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 -gas-eous release even though most will produce concentrations far below detection limits. The design objectives of the Crystal River Unit i
3 plant (insofar as environmental media concentrations are concerned) are that the radioactivity concentrations in the environment in the vicinity of the Crystal R$ver Plant, assuming that radioactivity from sources other than the Crystal River plant are insignificant, sho~uld not exceed, over a long term, values greater than the preop'.ational baseline median concentration values plus the maximum conce: : ration increase for design release value's on Table 3.2-6.
Detailed specifications for critical pathway Environmental media are divided into three major protection elements: (1) milk (an/or green leafy vegetable samples); (2) all other media, because of the basic differences in reporting requirements for I-131; and (3) external gamma radiation.
3.2.1 Milk and Green Leafy vegetables Specification (Program Element)
Samples of milk shallbe taken from locations and at frequencies listed in Table 3.2-2 and shall be analyzed according to the routine listed in Table 3.2-2. Analysis shall te carried out within eight days (one I-131 half-life) of sampling. Suitable analytical procedures shallbe used to determine the radiciodine concentration to a sensitivity of 0.5 picoeuries per liter of milk at the time of sampling. For act-ivity levels at or above 0.5 picorcuries per liter the overall error (one sigma confidence level) of the analysis shallbe within i 25%.
Results will be reported, with associated calculated error, as picoeuries of I-131 per liter of milk at the time of sampling.
If for any reason, milk samples listed in Table 3.2-2 are not available, green leafy vegetable sabples shallbe substituted for the above milk specification. The time of analysis should be similar to milk samples however, the overall error should be within 1 50%. All deviations from the sampling schedule shall be described in the semi-annual reports.
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 information from county agricultural agents or other reliable sources.
l If it is learned from this census that milch cnimals are present at a location which yields a calculated infant thyroid dose greater than from previously sampled aninals, the new location shall be added to the surveillance program as soor. as practicable. The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing season during which the census was con-ducted. Also, any location from which milk can no longer be obtained may be dropped from the surveillance program af ter notifying the NRC in writing of the reasons for this action.
i ~
T l
4 3-10 l
-3.2.2 Critical Pathway Media Other Than Milk, Green Leafy Vegetables or External Radiation Specification Samplesshall be taken from locations and at frequencies listed in Table 3.2-2 and will be analyzed according to the rcutine listed in , Table 3.2-2 using procedures which shall provide . concentration values with minium detectable limits which are equal to or less than those listed in Table 3.2-5.
Both the preoperational environmental surveillance results (Table 3.2-2) and the maximum expected concentration increase due to the design releases (Table 3.2-6) have been summarized. The control station value for each media, radioiosotope and station will be defined as either (1) the upper 95% percentile value from the pre-operational program, (1) the upper 95 percentile value from operational stations outside of the plant's influence, whichever is smaller.
3.2.3 External Radiation Specification Ambient external radiation levels shall be measured at 3 scations and frequencies listed in Table 3.2-2 using procedures which will provide Tadiation level values with adnimum detectable increases over pre-operational mean background which are equal to or less than that listed in Table 3.2-5.
Reporting Requirements The results of the radiological monitoring program shall b'e reported on a routine basis as specified in Section 5.6.1. In addition, measurements of radioactivity in critical pathway environmental media samples shall be reported on a nonroutine basis as described in Section 5.6.2.
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3-11 TABLE 3.2.1 -
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971 - 1974
- . operational 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) r- Water, Surface Gross (a) 19. pCi/1 s
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-54 (a) (a) 1-131 , (a) (a)
Water, Precipitation 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)
Hn-54 (a) (a)
I-131 (a) (a)
O 4
r 3-12 *
, TABLE 3.2-1
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/1 (b)
Ba-140 (a) 11. pCi/kg 1 Cs-137 9a) 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 l Ra-226 (a) 600. p Ci/kg )
Th-232 (a) 7. pCi/kg )
Zr-95 (a) (a) !
Ru-106 (a) (a) l Air Gross S 0.029 pCi/kg 0.120pCi/kg Ba-140.. (a) 0.016 pCi/m Cs-137 (a) 0.013 pCi/m3 Zn-65 (a) (a)
Mn-54 (a) (a) 3 I-131 (a) 0.004 pCi/m K-40 (a) (a)
Ra-226 (a) 0.241 pCi/m 3 Th-232 (a) 0.008 pCi/m3 Zr-95 0.003 pCi/m3 0.043 pCi/m 3 Ru-106 0.025 pCi/m 3 0.216 pCi/m 3 Ce-144 0.003 pCi/m3 0.172 pCi/m 3 Milk Sr-90 4. pCi/1 6.pci/1 -
Cs-134 (a) (a)
I-131 (a) (a)
Ha-140 (a) (a)
Co-58 (a) (a)
Co-60 (a) (a)
Ma-54 (a) (a)
Zr-95 (a) (a)
Cr-137 (b) (b) 9 l
3-13 * -
TABLE 3.2-1
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971 - 1974(Cont'd)
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)
Hn-54 (a) (a)
I-131 (a) (a)
- K-40 (b) (b)
Ra-226 (a) 2200. pCi/kg Th-232 (a) 300. pC1/kg Zr-95 40. pCi/kg 150. pCi/kg Ru-106 0. pCi/kg 330, p':i/kg Small Terrestrial Ba-140 (a) (a)
Animals Cs-137 (a) 80. pC1/kg 2n-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) -
- 70. pCi/kg Zr-95 (a)
Ru-106 (a) (a)
Total Deposition Ba-140 3 pCi/m2-day 22 pCi/m22-day '
Cs-137 (a) 6 pCi/m2-day Zn-65 (a) 7 pCi/m -day l Mn-54 (a) (a)
I-131 (a) (a j K-40 (a .03g/m}-dgy j Ra-226 20pCi/m}-day 508. pCi/m2-day Th-232 (a) 6. pCi/m -day '
Zr-95 (a) 13. pCi/m22 -d*7 Ru-106 (a) 152, pCi/m -day j
1 e
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- # ~*
3-14 TABLE 3.2-1
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. pCi/kg Mn-54 (a) (a) 1-131 (a) (a)
K-40 (a) 2.2 g/kg Ra-226 (a) 534. pCi/kg Th-232 (a) (a)
Zr-95 (a) (a)
Ru-106 (a) 82. pCi/kg Blue Crab Ba-140 (a) 55. pCi/kg Cs-137 (a) 75. pCi/kg Zn-65 (a) 127. pCi/kg Hn-54 (a) 24. pCi/kg f I-131 (a) (a)
K-40 1.7 g/kg 2.4 g/kg Ra.-226 1325. pCi/kg 3600. pCi/kg
~
Th-232 92 pCi/kg 170. pCi/kg Zr-95 (a) 13. pCi/kg Ru-106 (a) (a)
Herbivorous Fish Ba-140 (a) 50. pCi/kg Cs-137 (a) 110. pCi/kg 2n-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. pCi/kg Ru-106 (a) 90. pCi/kg S
l .
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. ^ 3-15 TABLE 3.2-1
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971 - 1974(Cont'd)
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. pCi/kg Mn-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) r Shrimp Ba-140 (a) (a)
- Cs-137 (a) 37. pCi/kg Zn-65 (a) (a)
- Mn-54 -
(a) (a) 1-131 (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 Co-58 (a) (a)
(Oranges) Co-60 (a) (a)
Ba-140 (a) (a)
Sr-90 105. pCi/kg 130. pCi/kg Cs-134 (a) (a)
Cs-137 (a) (a)
Zn-65 (a) (a)
Mn-54 (a) (a)
I-131 (a) (a) l I
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~'
I 3-16 TABLE 3.2-1 4
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVEILLANCE RESULTS 1971-1974 (Cont'd)
Preoperational Concentrations Environmental -
Media Nr..'.de 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 An-65 (a) 589. pCi/kg Mn-54 (a) (a)
I-131 (a) (a)
Ru-106 (a) (a)
Aquatic Plants Ba-140 (a) 75. pCi/kg and Grasses 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. pCf/kg Th-232 (a) 280. pCi/kg Ru-105 (a) 360. pC1/kg Zr-95 18. pci/kg 157. pCi/kg External Radiation All 62.nrem/yr (b)
Ocean Sediment Ba-140 (a) (a)
Cs-137 (a) 250. pCi/kg Zn-65 (a) (a)
Hn-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
i 06
~
. 3-17 l i
4 TABLE 3.2-1
SUMMARY
OF PREOPERATIONAL ENVIRONMENTAL SURVILLANCE 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 values will be provided for the radionulcides for each environmental media classification listed on Table 4.2- or values of zero will be assumed.
4 e
6
e 3-18
. V.
AIR 904mt RELEASES
, Leeuto RELEASES gg E E T ERN AL R408ATion SEA WATER 1
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l e i F04ASE SE0lM ENTS CAUSTACCA 1'
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CRITICAL PATHWAYS AIRSORNF RELEASES LIQUID RELEASE 3 ir
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PLANTS
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OTHER MONITO RE D PA TH w A) >
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! Figure 3.2-1 Environmental Medio and Exposure Pothways
TABLE 3.2-2 GENERAL PATHWAY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Pathway Sample Sample Sampling / Collection Analysis Significant Type Stations Frequency Routine Radionuclides Air External C04,C07,009 Continuous / Quarterly TLD Xe-133, KR-88 Submersion Radiation C18,C24,C40 C41,C42,C43, C14H,C14M, e C14G,C46 Air Air C04,C07,C18 Continuous / Weekly Gross B and I-131 -
Inhalation C24,C40,C41 I-131 weekly.
C46 i y-spectral on monthly composite.
Sr-89,90 of quarterly composite . Y U
Precipita ' Total C04,C24,C40 Continuous / Monthly H-3, y-s:uctral Cs-134,Cs-137,H-3 tion Deposition analysis I-131 Sea Water Water C01,C09,C13 -a - Monthly. y-spectral analysis, Cs-134,Cs-137,I-131, C14H,C14M,C14G A Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of beginning composite for Sr-89, discharge of evap. condensate 90,H-3 quarterly
analysis Grt i 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 C01,009,C14H Semi-Annual .*Extended y-Spectral Cs-134,Cs-137,I-131 External & Sediments C14M,C14G Analysis; Sr-39,90 Sea Food Chain
. *See Table 3.2-5 i
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Figure 3.2-2 Off Site Sampic Station t.ocations
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. 3-26 h-TABLE 3.2-5 .
- TYPICAL MINIMUM DETECTABLE CONCENTRATIONS Cross Beta In air 1 pCi/m By Nhans of Y Spectral Analysis .
Nb99m 10 pCi/1*
Co-58 . 10 pCi/3 Ba-140 .
10 pCi/1 Cs-134 10 pCi/1 Cs-137 10 pCi/1 Zr-95-Nb-95 10 pCi/1 1-131 10 pCi/1 Tritium Unenriched 200 pCi/1 Enriched ,, 30 pCi/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 arem/yr.
- Units of pCi/1 pertain to madia of unit (1g/ml) density
' ** EPA Report " Environmental Radioactivity Surveillance Guide" -
4 ORP/SID 72-2, June 1972. Table 2, Page 11.
- e
- 3-27 .
( .
Table 3.2-5 TYPICAL MINIMUM DETECTABLE CONCENTRATIONS (Con.'t) -
, Extended Cama Spectral Analysis (Celi-Typical)
Cr-51 60 pCi/1*
. Mn-54 10 gici/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
'Rb-91m . 10 pCi/1 Rb-92 150 pCi/1 Rb-93 100 pCi/1 Zr-95 20 pCi/1 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 1-131 ,, 10 pCi/1 1-132 10 pCi/1 I-133, 10 pCi/1 1-134 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 pCi/1 Ba-140 30 pCi/1 .
- Units of pCi/1 pertain to media of unit (Ig/n.D density
3-28 -
- TABLE 3.2-6 , (
MAXIMUM CONCENTRATION INCREASES FOR DESIGN RELEASES Environmental -
Media Nuclide Concentration Increase Air Cases 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/m3
- Xe-133m 55. pCi/m3
'Ke-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 O.08 pCi/m 3 I-133 Air None Particulates Milk I-131 .38 pCi/m3 (4 milo- TNi) I-133 -
.014 pCi/m3 Grasses 1-131'
~
7.3 pCi/m3 Vegetables.. I-133 .25 pCi/m3
(.9, miles ENE)
External Camma 2.2 mrem /yr.
Radiar. ion *
~(~ D ischarge Canal) i G
l I
- j
3-29 t
e TABLE 3.2-6 MAXIMUM CONCENTRATION INCREASES FOR DESICN RELEASES (Con't.)
Elnvironmental Nuclide Concentration Increase (pCi/kg)
Media Fish Crab Shrimp Algae Sen Life H-3 380. 380. 380. 380.
(Diccharge Cr-51 .0046 .046 .046 .046 Can11) 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 .0051 .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 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. "
1-132 .74 3.7 3.7 37. l I-133 2.3 11. 11. 1100. 1 I-134 .0076 .038 .038 3.8 I-135 .24 1.2 1.2 120.
Cs-134 13. 21. 4.2 4.2 l Cs-136 3.3 5.5 1.1 1.1 l Cs-137 10. 17. 3.5 3.5 l Cs-138 .061 .1 .02 .02 I Ba-140 .000046 .000046 .000046 .0015 l i -
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EN
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TABLE 3.2-6
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MAXIMUM CONCENTRATION INCREASES FOR DESICN RELEASES
'(Con.'t)
Environmental Media Nuclide Concentration 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 .0iOO12 pCi/1 .
Y-91m .00006 pCi/1
,Y-91 .031 pC1/1 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 pCi/1 Te-129 .00009 pCi/1 Te-131m .000009 pCi/1 Te-132 .00029 pCi/1 1-130 .00026 pCi/1 I-131 .76 pC1/1 I-132 .037 pCi/1 1-133 .11 pCi/1 1-134 .00038 pCi/1 ,
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 pC1/1 e
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TABLE 3.2-6 .
. MAXIMUM CONCENTRATION INCREASES FOR DESIGN RELEASES (Con.'t)
Envireenmental
- Hedia Nuclide Concentration Increase (pC_1/m2) m ilim.ni-40 year HulIslup Cr-Si .13 (DJscharge Mn-54 .56 Canal) Fe-55 5.8
- Fe-59 .057 Co-58 4.4 Co-6R 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 f Zr-95 .022 Nb-95 .013 Mo-99m ., 15.
Tc-99m .077 Te-127m .19 Te-127 .00067 j Te-129m .5 Te-129 *
.00045 1 Te-131m .0011 l
.Te-132 .094 1 I-130 .
.014 I I-131 .- 610. l I-132 .35 l I-133 10. '
I-134 .0014
- I-135 .34 Cs-134 31000.
Cs-136 140.
Cs-137 220,000.
Cs-138 .0045 Ba-J40 .019 l
1 1
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4.0 SPECIAL SURVEILLANCS, RESEARCH, OR STUDY ACTIVI ES s "4.1 THERMAL PLUME DETFRNINATION DURING UNIT 3 OPERATION
. Objective To establish the location and size of the thermal plume during normal operation, under conditions of high and low tide at.d maximum and minimum intake temperature; to provf de data to verify the mathematical and physical modele 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 months 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 ceasurement 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 cycleshall be tested. The measurements should allow for construction of the isothermal maps with 1.0*F above ambient costour intervals. These tests shall be carried out with all three Units operational and un' der 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 computer run with parallel parameters: (a) plant conditions (condenser flows, intake temperature, discharge temperature, loading, etc.) of all three units. (b) hydrologi. cal conditions (tidal stage, salinity traverses, etc., (c) meteorological conditions (wet and dry bulb temperature, humidity, windspeed, wind direction, solar radiation, etc.).
The field survey measurements shall be compared to the results of the computer runs. Any modifications needed in either the physical model or the mathematicel 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.
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4.2 INTAKE VELOCITY DETE10fINATION .
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 Velocity currents shall be measured ~o the nearest 0.1 using a 711 mash-Mc 51rney electromagnetic . dsetion currentmeter or its equivalent. Measurements shall be =ade at the surface, 3' and 6' elevations at each side of the canal, and 3' intervals from the surface at mid-canal during normal operation of all three units within a period of one year after startup of Unit 3.
4.3 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 c' 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 With-lacoochee waters, near-canal regions would be affected by scoured.
canal suspended sediments. These particles would most likely be - .
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 River-Barg~e Canal complex.
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Sediment levels and particle size are being investigated in areas of concern and changes in the community structure can be detected.
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5-1 5.0 ADMINISTRATfVECONTROLS
_0bjective To define the organization, assign responsibilities, describe th'e envrionmental surveillance procedures, provide for a review and audit function, and prescribe the reporting requirements in order to insure continuing protection of the environment and implement the Environmental-Technical Specifications.
5.1 ORGANIZATION
..,o, The organization responsible for environmental protection, environ-mental monitoring and the implementarfon of the Environmental Technical Specifications, 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 The responsibility for the conduct of the preoperational environmental monitoring program described in Section 3 and special studies described in Section 4 is that of the Quality and Environmental Department under the direction of the Director of Environmental and Licensing Affairs.
Upon the issuance of an operating license the responsibility for the cooduct of the postoperational environmental monitoring program and the implementation of Environmental Technical Specifications becomes the responsibility of the System Operations Department.
The plant organization is responsible for the development of Operating and Surveillance Procedures described generally in Section 5.5 and supplying field data to the }anager Nuclear Operations as !
required by Section 2, 3 and 4 of the Environmental Technical Specifi- '
cations.
The Manaaer Nuclear Operations 'is responsible for consultant contracts, State and local regulatory agreements, ascembly of data preparation of reports required by Section 5.6 of these Environmental Technical Specifications, and making recommendations to improve environmental protection practices.
All reports and correspondence with the NRC regarding the Environmental Technical Specifications shall be approved and signed by the Vice President, System Operations. The Nuclear Plant Superintendent shall, however, make reports by telephone and telegraph of any incident or occurrence requiring reporting within 24 'ours or less, as required in Section 5.6.
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5'2 ,
PRESIDENT ,
SENIOR VICE PRESIDENT VICE PRESIDENT SYSTE!! ENG. & OPERATIONS AND GENERAL COUUSEL VICE PRESIDENT ASSI.STANT VICE PPISIDENT SYSTEM OPERATIONS QUALITY & ENVIROD' ENTAL DEPARTMENTS 1
- DIPICTOR DIRECTOR PO'JER PRODUCTION ENVIRONIENTAL & LICENSING AFFAIRS m
MANAGER NUCLEAR OPERATIONS PLANT SUPERINTENDENT l
l PLANT STAFF l
Figura 5'1-1 Organization for implementing Environmenta. Technical Specifications
s - *
' 3 5.3 REVIEW AND AUDIT The FPC corporate Quality Assurance organization under the direction of the Director of Quality Programs 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 Programs that is independent of the System Operations Department.
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 However, Senior Vice President, System Engineering and Operations.
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 NRC in each Environmental Operating Report. See Section 5.6.1.
- b. Review and make recommandations 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 (nr which would affect the J evaluation of the plant's environmental impact as described in l
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.
- e. Review reported instances of violations of Environmental Technical Specifications, the reaching of specified reporting Where investigation levals, and abnormal environmental occurrences.
indicates, evaluate and formulate recommendations to prevent recurrence.
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I PRESIDENT t
, SENIOR .' NUCLEAR VICE PRESIDENT ,
t VICE PRESIDENT CENERAL REVIEW COMMITTEE AND .-
% SYSTEM ENG. & OPERATIONS CENERAL COUNSEL LT
% /
t VICE Pl?ESIDE' T PLANT ASSISTANT VICE PRESIDENT ;
SYSTE! OPERATIONS REVIEW C0FDitTTEE QUALITY & ENVIRONMENTAL DEPARTMENTS ,
- I I !
DIRECTOR DIRECTOR POWER PRODUCTION QUALITY PROGRAMS I
Figure 5.3-1 Organization for Independent Review and Audit
. . - - - .. .. . . . . n .~ ...... . -
/
5-5 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 LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Immediate remedial actions as permitted by these technical specifi-cations shallbe implemented until such time as the limiting condition for operation s met.
5.4.2 The occurrence 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 separate report for each occurrence in writing to the 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.
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5.4.4 The Vice President, System Operations, shall report the occurrence ,
to the NRC as specified-in Section 5.6.2. '
5.5 PROCEDURES j 5.5.1 Explicit written procedures, including applicable check-cff lists and instructions, shall be prepared for the implementation of the
~
monitoring requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for operation of all 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 instrurents 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 procedures implemented by plant staff personnel described in Section 5.5.1 above, and changes the~reto, shall be revievel as specified in Section 5.3 and approved by the Nuclear Plant Superintendent prior to l
i implementation. Temporary changes to procedures which do not change the l l
intent of the original procedure may b.e made, provided such changes are approved by two members of the plant management staff, one of whom holds l l a senior operators license. Such changes shall be documented, subsequently l l
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5-6 reviewed and approved by the Plant and Nuclear General Review Committees.
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All changes to procedures utilized by contractors to implement the environmental monitoring programs described in Section 3 shall be reviewed and approved by the Manager, Nuclear Operations. _
5.5.3 Prio* 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 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 Connittee for review.
- b. If the Nuclear Plant Superintendent desires to make a change in the facility or Operating Procedures, or to conduct 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, or experiment until he r has referred the matter to the Nuclear General Review
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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 Nuclear-Regulatory Commission under the terms of said license, it shall so report in writing to the Nuclear Plant Superintendent, together with a statement of the reasons for the Committee decision and the Nuclear Plant Superintendent may then proceed with the change, test, or experiment. If on the other hand the Committee is of the opinion that approval of the Nuclear Regulatory Co= mission is required, the Committee shall prepare a request for such approval, including an appropriate environmental analysis in support of the rec,uest, and following Committee concurrence, forward its report to the Senior Vice President of System Engineering and Operations for his review with a copy to the .
Nuclear Plant Superintendent.
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5-7 5.6 PLANT REPORTING REQUIREMENTS 5.6.1 Routine Reports .
A. Annual Environmental Operating Report (1) Nonradiological Volume A report on the nonradiological environmental surveillance
. programs for the previous 12 months of operation shall be submitted to the Director of Inspection and Enforcement (with copy to Director.,
Office of Nuclear Reactor Regulation) as a separate Volume (#1) of the Annual Environmental Operating Report within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The report shall include summaries, interpretations, and statistical evaluation of the results of the nonradiological environmental surveillance activities (Section 3.0) and the environmental monitoring programs required by limiting conditions for operation (Section 2.0) for the report period. A comparison with preoperational studies, operational controls (as appropriate),
and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on
,- the environment shall be provided. 'If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem. .
(2) Radiological Volume A report on the radiological environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of Inspection and Enforcement (with copy to Director, Office of Nuclear Reactor Regulation) as a separate volume (#2) of the Annual Environmental Operating Report within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report . period, including a comparison with preoperational studies, operational controls (as appropriate) and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.
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< Results of all radiological environmental s.amples taken shall
- be summarized on an annual basis following the format of Table 5.6-1.
In the event that some results are not available within the 90 day period, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. ,
B. Semiannual Operating Report - Radioactive Effluents A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Inspection and Enforcement (with copy to Director,0ffice of Nuclear Reactor Regulation) as part of the Semiannual Operating Report within 60 days after Janauary 1 and July 1 of each year. The perio'd of the first report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in USNRC Regulatory Guide 1.21, with )
data summarized on a quaterly basis following the format of l Appendix B thereof. 1 The report shall inicude a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in USNRC Regulatory Guide 1.21, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in the 4 atmosphere shall be reported in accordance with Regulatory Guide 1.21.
5.6.2 Non-Routine Reports A. Limiting Condition for Operation Exceeded In the event that a limiting conditiIon for operation is exceeded including any mylanned release of radioactive material from the site, or an event involving a significant adverse environment impact occurs, a report will be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Office of Inspection and Enforcement followed by a written report with a copy to the Director, Office of Nuclear Reactor Ragulation within 15 days. The telegraph renort will quantify the occurrence, its c&uses and, if aspects o~ i;.0 Cryctal River Unit 3 opera-tion 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 poJrible. .
i B. Non radiological Report Levels In the event that a nonradioactive reporting level is reached, a written report shall be made within 30 days to the Director of the Office of Inspection and Enforcement with a copy to the Director of Office of Nuclear Reactor Regulation. The report sha11 describe, analyze and evaluate the occurrence, including extent and magnitude
^ '
of impact; describe the cause of the occurrence; and if aspects of the Crystal River Unit #3 operation are among the causes, indicate
'the correction action taken to preclude reptition of the occurrence.
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. 59 s. l
= l TABLE 5.6-1 ItEPORTING OF RADIOACTIVITY IN THE ENVIRONS Factitty Docket No. Reporting Period A. Sample Results Averaae Ouarterly pesults Analysts Results Frequency and}/ (specify radio-Sample Imeetto Tvoe of Samples nueltde or entity) Remarks (1) External Radiation (2) T11terable Atrborne
- a. Particulate Filters 1) 2)
etc.
- b. Charcoal Tilters 1) 2)
etc.
(3) WaterM a.
b.
etc.
(4) Food (Human) a.
~
b.
etc.
(5) Other Medle
- a. Vegetation (include pasture and other animal foodstuffs)
- b. Sotts .
- c. Sediments
- d. Tish
- e. etc.
ExplAfn any unusual measurements or deviation from sampling schedule.
Use the following units; external radiation, mrem / quarter: filterable airborne, water and milk, pct /ml; soll, pC1/m 2 (spectfy depth). precipitation, pC1/m2 : stream sediments and terrestrial and aquatte vegetation, PC1/ dry gm; other media, specify units.
Spectfy location and its distance and direction from the facility, and indicate which is used for background.
Indicate whether precipitation, surface, ground, Lake, river, ocean, etc.; specify drinking water.
Use separate table for each quarter.
Type of sample means either greb, continuous, proportional, compostte, etc. ~
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5 10 B. Radiological Reporting Levels In the event a report level specified below is reached, a report shall be made within the designated time period to the Director of Inspection and Enforcement with a copy to the Director of office of Nuclear Reactor Regulation.
(1) Radioactive Discharge If measured rates of release of radioactivity in the environ-ment, averaged over a calendar quarter, exceed the design objective rates as specified in specifications 2.4.1.H for liquid effluents and in 2.4.2.H for airborne effluents a report of the causes of the release rates and of a proposed program of' action to reduce the release rates: will be submitted within 30 days from the end of the quarter during which the release occured.
1 (2) Radiological Environmental Monitoring Me dia Other Than Milk, Green Leafy Vegetables or External Radiation
'~
If a single measured value of radioactivity concentrations in critical pathway environmental medium samples identified in Section 3.2 exceeds ten times the control station value as' defined in Section 3.2, a written notification including an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result shall be submitted within one week.
If the average of the values of radioactivity concentrations in any critical pathway environmental media samples measured during a calendar quarter exceeds four times the control
! station value as defined in Sectica 3.2 a written notification including an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result shall be submitted within 30 days. .
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Milk and Green Leafy Vegetables If milk samples collected over a calendar quarter show average concentrations of 4.8 picoeuries per liter or greater, a plan shall be submitted within thirty (30) days advising 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.
If individual milk samples show I-131 concentrations of 10 picoeuries per liter or greater, a plan shall*be submitted within one week advising 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.
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 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.
If individual green leafy vegetable samples collected in lieu of milk show I-131 concentration of 440 picoeuries per kilogram or greater, a plan shall, be submitted within one week advising 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.
External Radiation The results shallbe reported in routine reports as specified in Section 5.6.1. - -
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5.6.3 Changes -
A. A report shall be made to the Director of Office of Nuclear Reactor Regulation prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have, in the judgement of the applicant, a significant adverse effect on the environment or involves an environ-mental matter or question not previously reviewed and evaluated by the USNRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
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. t 5-12 B. Request for changes in environmental technical specifications shall be submitted to the Director of Office of Nuclear Reactor Regulation for reriew and authorization. The request shall include an evaluation of the impact on the change and a supporting benefit-cost analysis.
5.7 ' RECORDS RETENTION 5.7.1 Records and logs relative to the following areas shallbe 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 e specifications shall be retained for five years.
5.8 SPECIAL REQUIREMENTS 5.8.1 Accumulated debris collected from the traveling screens shall be routinely removed and buried on-site.
5.8.2 The chemical-industrial waste water treatment system shallcollect and transport all water wastes to the percolation / evaporation ponds.
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The system is shown disgramatically on Figure 5.8-1.
5.8.3 Hunting is prohibited on the site.
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POWER PLANT * -
EOUIPM CNT l-DRAINS
. SAMPLE POINT
_f HOLDING POND NO.1 POWER PLANT _
FLOOR DRAINS Jb WATER TREATMENT OVERFLOW DEMINERALIZER WASTE DRAINS SAMPLE BOILER AND AIR POINT HEATER WASH _ I __ HOLDING DRAINS '
POND NO.2 BOILE R -
BLOWDOWN SOLIDS IN LIME SOFTNER _ SOLIDS 1 DRUMSFOR 1
BLOWDOWN AND SEPARAROR DISPOSAL WASTE DR AINS f
CLARIFIED WATER RECYCLED TO SOFTNER 1
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l Figure 5.8-1 Chemical-Industrial Waste water Treatment syst .n ,
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