Text

Environmental Technical Specifications, Appendix B to Operating Licensing for Florida Power & Light
	ML18113A480
Person / Time
Site:	Saint Lucie
Issue date:	02/14/1975
From:	; Florida Power & Light Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML18113A480 (73)
	v • d • e

Environmental Technical Specifications to 0 eratin Licensin No.

For Florida Power 6 Li ht's St. Lucie Unit No.

1 Docket No. 50-335

TABLE OF CONTENTS Pa<ac 1.0 DEFINITIONS 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9

,1. 10

l. 11

l. 12

1. 13

l. 14

l. 15

1. 16

1. 17

1. 18 1.19 1.20 1.21 National power emergency A regional emergency.

,Reactor emergency Circulating water system Frequency definitions follow Free Available Chlorine Combined Available Chlorine Total Residual Chlorine Intake Temperature Discharge Temperature Dissolved Oxygen Limiting Conditions Salinity Dose Equivalent I-131 Channel Calibration Channel Check Channel Functional Test Abnormal Release Batch Releases

'Continuous Release Determined (or a Determination) l-l l-l l-l l-l l-l 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-3 1-3 1-3 1-3 1-3 1-3 1-3 2.0 'IMITINGCONDITIONS 2-1 General 2.1 2.2 2.3 2.4 thermal Chemical 2.2.1 Biocides 2.2.2 pH 2.2.3 Dissolved Oxygen (Reserved)

Radioactive Effluents 2-2 2-2 2-3 2-3 2-4 2-4 2-4 2.4.1 2.4.2 2.4.3 2.4.4 2.4.5 Liquid Effluents Liquid Release Limits Bases Gaseous Releases Gaseous Release Limits Bases (Reserved) 2-4 2-8 2-9 2-17 2-18

TABLE OF CONTENTS (Continued)

Pacae 2.4.6 Effluent Monitors 2.4.6.1 2.4.6.2 2.4.6.3 2.4.6.4 2.4.6.5 2.4.6.6 2.4. 6.7 2.4.6.8 Liquid Rad Waste Monitor Gaseous Radwaste Monitor Plant Vent Monitor Spent Fuel Storage Area Monitor Condenser Air Ejector Vent.

Steam Generator Blow-down Monitors Process Monitor Calibration Process Monitor Inoperability 2.4.7 Containerized Wastes 2-19 2-19 2-19 2-20 2-20 2-21 2-21 2-22 2-23 2-23 3.0 ENVIRONMENTAL SURVEILLANCE

-3.1 Non-Radiological Surveillance 3.1.A ABIOTIC 3.1.A.l Biocides 3.1.A.2

. Heavy Metals 3.3,.A.3.

pH 3.1.A.4 Dissolved Oxygen 3.1.A.5 Salinity

3. 1.A. 6 Temperature 3.1.B BIOTIC 3-1 3-1 3-1 3-1 3-2 3-2 3-2 3-3 3-3 a)

Benthic Organisms b)

Plankton c)

Nektonic Organisms d)

Macrophytes e)

Water Quality f)

Migratory Sea Turtles 3.2 Radiological Environmental Monitoring 4.0 SPECIAL SURVEILLANCE 6 SPECIAL STUDY ACTIVITIES

4. 1 Impingement of Organisms

'4.2 Land Management, 3-3 3-4 3-4 3-4 3-4 3-4 3-5 4-1 4-1

TABLE OF CONTENTS (Continued)

Pacae 5.0 ADMINISTRATIVE CONTROLS 5-1 5.1 5.2 5.3 5.4 5.5 5.6 Responsibility

'Organization Review and Audit Action To Be Taken If A Limiting Conditi'on Is Exceeded Procedures Reporting Requirements 5-1 5-1 5-1 5-4 5-5 5-5

5. 6.1 5.6.2 5.6.3 Routine Reports Non Routine Reports Changes in Environmental Technical Specifications 5-5 5-14 5-15 5.7 Records Retention 5-15

TABLE OF CONTENTS (Continued)

Pa<ac

., TABLES Table

2. 4. 1-A Table 2.4.1-B

Table

2. 4. 3-A Table

2. 4. 3-C Table 2.4.3-D Table 2.4.3-E Table 2.4.3-F Table 3.2-1 Table 3.2-2 Table

3. 2-3 Table 5.6.1-1 Table 2.4.3-B Batch Releases Steam Generator Blowdown (Continuous)

Gas Decay Tank Plant Vent Containment Purge Condenser Air Ejector Vent Spent Fuel Storage Area Main Stream Operational Environmental Radiological Surveillance Program Practical Reporting Limits Operational Environmental Radiological Surveillance Program Effluent and Waste Disposal 2-5 2-6 2-10 2-11 2-12 2-13 2-14 2-15 3-7 3-12 3-13 5-7 Table Table II Table I

5.6.1-A il

5. 6. 1-B

5. 6. 1-C Gaseous Effluents Summation of All Releases Gaseous Effluents Liquid Effluents Summation of All Releases 5-9 5-10 5-11 Table 5.6.1-D Table 5.6.1-E Liquid Effluents Solid Waste and Irradiated Fuel Shipments 5-12 5-13 iv FEB 14 1975

TABLE OF CONTENTS (Continued)

Pa<ac FIGURES Figure 3.2-1 Figure 5.2-1 Operational Radiological Surveillance Sampling Stations Florida Power

& Light Company Corporate Organization Environmental Affairs 3-6 5-2 FEB 14 1975

1.0 DEFINITIONS The definitions for terms used in these environmental technical specifications are listed below.

1.1 National ower emer enc Shall mean any event, causing authorized Federal officials to require or request that Florida Power 6 Light supply electricity to -points within or'ithout the State of Florida.

1. 2 A re ional emer enc Shall mean any of the following occurrences within the State of Florida:

(1) a catastrophic natural disaster including hurricanes, floods,'nd tidal waves; or (2) other emergencies declared by State, county, municipal, or'Federal authorities during which an uninterrupted supply of electric power is vital to public health and safety.

1.3 Reactor emer enc Shall mean an unanticipated equipment malfunction necessitating prompt remedial action to avoid

.endangering the public health or welfare.

1.4 Circulatin water s stem Comprised of the following; velocity cap, intake pipe, intake canal, discharge

canal, discharge pipe, "Y" port discharge and miscellaneous mechanical devices.

The recirculation canal is included, if constructed.

1.5 Fre uenc definitions follow:

Daily Not less than 360 times per annum.

Weekly Not less than 48 times per annum interval may vary by 3 days.

Monthly Not less than 10 times per annum interval may vary by 15 days.

Quarterly Not less than 4, times per annum interval may vary by 30 days.

Semi-annually Not less than 2 times per annum interval may vary by 60 days.

Refueling at refueling intervals not to exceed 24 months.

l. 6 Free Available Chlorine The amount of residual chlorine consisting of hypo-chlorite ions (OC1), hypochlorous acid (HOC1), or a combination thereof.

la7 Combined Available Chlorine The amount of residual consisting of chlorine combined with ammonia nitrogen or nitrogenous compounds.

1.8 Total Residual Chlorine The amount of free and combined available chlorine present in water.

la9 Intake Tem erature The temperature of the cooling water as measured in the intake canal near the subaqueous intake pipe east of State Road A-l-A.

1.10 Dischar e

Tem erature The temperature of the cooling water as measured near the terminus of the discharge canal.

1.11 Dissolved Ox en Oxygen dissolved in the condenser cooling water, and expressed in milligrams per liter.

1.12 Limitin Condition Those conditions to be imposed=on plant effluents and operating practices which may have an adverse impact on the environment.'.

13

~Salinit The total amount of solid material in grams contained in one kilogram of sea water when all the carbonate has been converted to oxide, the bromine and iodine replaced by chlorine, and organic matter completely oxidized.

1.14 Dose E uivalent I-131 Dose equivalent I-131 shall be that concentration of I-131 (pCi/gram) which alone would produce the same dose as the quantity and isotopic mixture of iodine actually present.

1-2

1.15 Channel Calibration A Channel Calibration shall be the adjustment of the channel output such that it responds with specified 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.

1.16 Channel Check A Channel Check shall be the qualitative assessment of channel behavior during operation by observation.

, This determination shall include, where possible, comparison of.the channel indication with other indications derived from independent instrument channels measuring the same parameter.

1.17 Channel Functional Test A Channel Functional Test shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify Operability including alarm and/or trip functions.

1.18 Abnormal Release An uncontrolled or unplanned release of radioactive material from any plant system designed to act as a

boundary for such material in an amount of significance with respect to limits prescribed in Technical Specifications.

1.19 Batch Releases Discontinuous release of gaseous or liquid effluent which takes place oyer a finite period of time, ususally hours or days.

1.20 Continuous Release Release of gaseous or liquid effluent which is essentially uninterrupted for extended periods during normal operation of the facility.

1.21 Determined (or a'etermination)

A quantitative evaluation of the release or presence of radioactive material under a specific set of conditions.

A determination may be made by direct or indirect measurements.

In some cases it may not be practical to make direct measurements of specific radionuclides in effluent or waste; e.g.,

the concentrations may be too low for measurement

.in a reasonable or practical volume of sample, certain 1-3

nuclides may be masked by other radionuclides in the sample, or as in the'ase of solid or concentrated wastes, it may be difficult to obtain a representative sample.

Under these circumstances, it may be more appropriate to calculate releases using previously established ratios with those nuclides which are readily measurable. 'uch a procedure would constitute a determination.

I 1-4 FEB 14 1975

2.0 LIMITING CONDITIONS General The circulating water system shall be operated to result, in an acceptable environmental impact.

Flexibility of operation is permitted, consistent with. consideration of health and safety, to ensure that the public is provided a'dependable source of power even under unusual operating conditions which may set forth in this specification, as provided below in 2.0.2 and 2.0.3.

2.0.2 2.0.3 During a national power emergency, a regional emergency, reactor emergency, or any time when the health, safety, or welfare of the public may be endangered by the inability of Florida Power

& Light to supply electricity from any other sources avail-able to it, the operating'.limits provided in this specification shall be inapplicable.

However, during such" emergencies, the operating limits shall not be exceeded except as is necessitated by the emergency.

Whenever, in accordance with paragraphs 2.0.1 and 2.0.2 above, Florida Power 6 Light exceeds the operating limits otherwise imposed, notification hall be made to the Director of the Region II Regional Office of the Office of Inspection and Enforcement, in accordance with 5.6.2.a.

2-1 FEB 14 1975

2.1 THERMAL r

Maximum Dischar e

Tem erature The purpose of this specification is to limit thermal stress to the aquatic ecosystem by limiting the temperature rise in he Atlantic Ocean, in the area of the subaqueous discharge, due to the plant discharge during operation.

S ecification:

The thermal discharge of St, Lucie Unit Ol shall comply to the specifications in and any amendments to Florida Power 6 Light's National Pollutant Dischaige Elimination System (N.P.D.E.S.)

Discharge Permit FL 0002208.

0 Monitorin Re uzrement.

A continuous temperature measurement, system shall be installed near the terminus of the discharge canal at mid-depth.

Temp-eratures shall be transmitted to the control room.

A continuous temperature monitoring station located within 500 feet from the primary monitoring device, shall be used as a backup system if the "primary system fails.

In this event this station shall be checked every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months until the primary. system is restored.

Bases:

The limitations provide reasonable assurance that the overall aquatic ecosystem in the area of the thermal plume will experience an acceptable environmental impact.

The placement of the temperature monitoring instrument at the control struc-ture will give the temperature of the discharge water immed-iately before mixing with the receiving water.

The placement of the temperature sensor at mid-depth in the discharge canal has been shown by temperature measurements at other depths in the canal to be representative of the discharge water entering the receiving stream.

2.2 CHEMICAL Ob'ective':

The purpose of these specifications is (1) to minimize impacts to the quality of the Atlantic Ocean, (2) to protect the local biota from lethal and sublethal effects of exposure to chemical discharges due to operation of the plant, (3) to assure that continued multiple use of the receiving waters by human populations is protected, and (4) to control the quality of the receiving medium.

2-2 FEB 14 1975

2. 2. 1 Biocides S ecification:

Free available chlorine near the terminus of the discharge canal shall not exceed 0.2 mg/1 on a daily average or 0.5 mg/1 at any one time. If this level is exceeded, adjustments to the injection system shall be made to reduce the concen'tration and each succeeding chlorination period shall be monitored until the concentration is within the specification.

Monitorin Re uirements:

A grab sample of condenser cooling water shall'e taken weekly near the terminus of the discharge canal and analyzed for total residual chlorine and

-free available chlorine.

The samples shall be taken during the period of chlorination.

The time of beginning the chlorination and when the sample was taken shall be logged.

Bases:

When injected, chlorine is diluted by the cooling water and, consumed in the process of controlling slime.

To be sure that enough chlorine is injected to control the slime, the residual chlorine concen-tration will be approximately 1 mg/1 at the condenser outlet.

This concentration corresponds to a concen-tration; in the immediate vicinity of the discharge of less than 0.2 mg/1.

The limits set forth provide reasonable assurance of an acceptable environmental

'mpact.

2. 2. 2 p.'I S ecification:

The pH of effluents at the terminus of the discharge canal shall comply to the specifications in and any amendments to Florida Power 6 Light's National Pollutant Discharge Elimination System (N.P.D.E.S.')

Discharge Permit FL

0002208, and the State of Florida's Water Quality Standards.

Monitorin Re uirement:

Grab samples shall be taken on a daily basis at the terminus of the discharge

canal, and the pH determined with a pH meter of pH recorder.

2-3 FEB 14 19?5

2. 3 (Reserved) 2.4 RADIOACTIVE EFFLUENTS Ob'ective:

To establish conditions for the release of liquid and gaseous containing radioactive materials and to assure that all such releases are within the limits specified in 10CFR20.

In addition, a reasonable effort shall be made to control the rate of release of radioactive materials in liquid and gaseous waste discharged from the plant to unrestricted areas as low as practicable.

2.4.1 Li uid Effluents S ecification:

A. If the release of radioactive materials in liquid wastes, when summed over a calendar quarter exceeds 5 curies, excluding tritium and dissolved gases:

l.

An investigation shall be made to identify the cause for such release rates.

2.

A program of action to reduce such release rates shall be defined and initiated.

B. If the experienced release of radioactive material in liquid waste, when summed over a calendar

. quarter, exceeds 20 curies, excluding tritium and dissolved gases, immediate action shall be taken as may be appropriate, including reductions in power level, to assure that such release, rates are reduced.

E Surveilla'nce Re uirement:

See Tables:

2.4.1-A 2.4.1-B 2-4 PEB 14 i9i5

TABLE 2.4.1-A BATCH RELEASES FREQUENCY TYPE OF ACTIVITY OF ANALYSIS REQUIREMENT OR SENSITIVITY Each Batch Gross activity Principal Gamma Emitting Nuclides (2) (3)

Liquid effluent monitor 1 x 10 pCi/ml

-7 5 x 10 yCi/ml Set to alarm and automatically terminate release One batch per month Weekly propor-tional composite (1)

Monthly propor-tional composite (1)

Quarterly porpor-tional composite (1)

Volume of release Volume of dilution water Resultant concentration in circulating water system Circulating water system Length of time of release Dissolved and entrained fission and activation gases (3)

Principal gamma emitting nuclides (2)(3)

Tritium Gross alpha Strontium 89 Strontium 90 Record Record Calculate and record Minimum of one main circulating water pump in operation while releasing.

Record 1 x 10

. vCi/ml 5 x 10 pCi/ml 1 x 10 7 uCi/ml 1 x 10 PCi/ml 5 x 10 8

PCi/ml 5 x 10

>Ci/ml SEE NOTES ON PAGE 2-.7 2-'5 FEB 14 1975

TABLE 2.4.1-B STEAM GENERATOR BLOWDOLUN (CONTINUOUS)

~ FREQUENCY TYPE OF ACTIVITY OR ANALYSIS REQUIREMENT OR SENSITIVITY Three times per seven days (max. time between samples is 72 hrs) once per 30 days continuous weekly (6)

Gross activity determination Isotopic analysis for Dose Equivalent Iodine 131 concentration (3)

Gross Activity (5)

Circulating water system Principal gamma emitting nuclides (2)

(3)

(4)

Tritium (4)

Volume of release/week (4)

Volume of Dilution water/

week (4)

Resultant concentration in circulating water system (4)

-7 1 x 10 pCi/ml 5 x J.O pCi/ml (for I-131 only) while discharging directly to circulating water system Minimum of one circulating water pump in operation while discharging 5 x 10 yCi/ml 1 x 10 yCi/ml Record Record Calculate and Record SEE NOTES ON PAGE 2-7 2-6 FEH 14 1975

(1)

A proportional sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(2)

(3)

When operational or other limitations preclude specific gamma radionuclide analysis of each batch, gross radio-..

activity measur'ements should be made to estimate the quantity and concentrations of radioactive material released in the batch, and a weekly sample composited from prop'ortional aliquots from each batch released during the week should be analyzed for the principal gamma-emitting radionuclides.

For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations.

Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using. observed ratios with those radionuclides which are measurable.

(4)

(5)

Only when activity is detected in steam generators by routine gross activity or Iodine-131 equivalent analyses.

Whencontinuous monitor is inoperable daily gross activity grab samples may be substituted.

(6)

These requirements only apply when discharging directly to circulating water system.

When discharging to'steam generator blowdown treatment facility, requirements will be as stated in Table 2.4.1-A "Batch Releases".

2-.7 FEB 14 19i5

2.4.2 Li uid Release Limits Bases The specifications in 2.4.1 provide reasonable assurance that the resulting annual exposure to the whole body or'ny organ of an individual from liquid effluents will not, exceed 5 millirems/year based on the generally expected distribution of isotopes.

The licensee is permitted the flexibili.tyof operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions but still remain within the concen-tration limits specified in 10CFR20.

At the same time it is expected that, using this operational flexibility

, under unusual operating conditions, the licensee shall exert every effort to keep levels of radioactive material in liquid wastes

as low as practicable and therefore than annual releases will not exceed a small fraction of the annual average concentration limits for unrestricted areas specified in 10CFR20 The minimum circulating water discharge flow, for one circulating water pump in operation 'is 121,000

gpm, and for one intake cooling water pump in operation, is 14,500 gpm.

The discharge of 5 curies of radioactivity into the circulating water flow in a calendar quarter, assuming an 80% operating factor, would result in an average concentration pf radioactivity in the discharge of about 1.2 x 10.

pCi/cc.

Release batch sampling will provide the data for determining and evaluating activity release rates and for record keep-ing.

2.4.3 Gaseous Releases 2.4.3.1 The rate of release of radioactive materials in gaseous

wastes, averaged over a calendar quarter, shall not exceed A., A total of 7 millicuries per second or, B.

For I-131 and 'particulate radionuclides with half life greater than 8 days, a

rate determined by Ei MPC.i 3

10,000 sec

Q. = release rate of the i radionuclide, 3.

curie/second.

MPCi = concentration values in Appendix B, Table II, Column 1, 10CFR20.

2.4.3.2 The total release rate of radioactive materials shall not exceed 122 millicuries per second averaged over any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Action:

2.4.3.1.1 An investigation shall be made to identify the causes for such release

rates, and 2.4.3.1.2 A program to reduce such release

rates, including a reduction in power level'if appropriate, shall be defined and initiated immediately.

Surveillance Re uirement:

2.4.3:;.3i, See Tables:

2.4 2.4 2.4 2.4 2.4 2.4

.3-A

.3-B

.3-C

.3-D

.3-E

.3 F 2-9..

FEB 14 1975

TABLE 2.4.3-A GAS DECAY TANK

'FREQUENCY TYPE OF'CTIVITY OR ANALYSIS'"

REQUIREMENT OF

.SENSITIVITY Each release Hourly during.

release Weekly Noble gases (1)

(4)

Particulates T 1/2>8 days (1)

(4)

Iodines (1)

(4)

Tritium Volume of'Release Length of time of release Gaseous effluent monitor Wind Speed Wind Direction 1

Differential Temperature Total Activity each gas decay tank in equivalent Xe-133(1)

-4 1 x 10 pCi/cc Note (3)

Note (2)

-6 1 x 10 pCi/cc Record Record Set to alarm and automatically terminate release Record Record Record 73,000 curies maximum allowable SEE NOTES ON PAGE 2-16 4

2>>10

TABLE 2.4.3-B PLANT VENT FREQUENCY TYPE OF ACTIVITY OR ANALYSIS REQUIREMENT OR SENSITIVITY Continuous Weekly Monthly Quarterly Gases (5)

(Gross Activity)

Particulate T 1/2 8 days (1) (4)

'odine-131 (4)

Noble Gases (1)

(4)

Tritium Iodine 133 (4)

Iodine 135 (4)

Gross Alpha (Particulate filter)

Strontium 89)(Particulate Strontium 90) filters)'onitor Note (3)

Note (2) 1 x 10 4 pCi/cc 1 x 10 6 pCi/cc Note (2)

Note '(2)

Note (3) composite of all weekly filters Composite of all weekly filters SEE NOTES ON PAGE 2-16 PEB la 1975

TABLE 2.4.3-C CONTAINMENT PURGE FREQUENCY'YPE OF ACTIVITY OR ANALYSIS Each release Hourly during release Noble Gases (1)

(4)

Particulate T 1/2

>8 days Iodines (1)

(4)

I Tritium Volume of Release Length of time of release Wind Speed Wind Direction

-Differential Temperature 1 x 10 pCi/cc Note (3)

Note (2)

-6 1 x 10 pCi/cc Record Record Record Record Record SEE NOTES ON PAGE 2-16 2-12 FEB 14 1975

TABLE 2.4.3-D CONDENSER AIR EJECTOR VENT FREQUENCY TYPE OF ACTIVITY OR ANALYSIS REQUIREMENT,OR SENSITIVITY Continuous (7)

Weekly (6)

Gross Activity (5)

I-131 (4)

Particulate T 1/2 )

8 days (1)

(4)

Monitor Note (2)

Note (3)

SEE NOTES ON PAGE 2-16 2-13 f'EB 14 1975

TABLE 2.4:3-E SPENT FUEL STORAGE AREA FREQUENCY TYPE OF ACTIVITY OR ANALYSIS REQUIREMENT OR SENSITIVITY Continuous (8)

Weekly (8)

Monthly (8)

Quarterly (8)

Gases (5)

(Gross Activity)

Particulates T 1/2 8 days (1)

'4)'odine 131 (4)

Noble Gases (1)

(4)

Tritium Iodine 133 (4)

Iodine 135 (4)

Gross Alpha (Particulate Filter)

Strontium 89 }(Particulate Strontium 90) Filter)

Monitor Note (3)

Note (2) 1 x 10-4 QCi/cc 1 x 10 6 pCi/cc Note (2)

Note (2)

Note (3)

Composite of all weekly filters Composite of all Weekly Filtexs SEE NOTES ON PAGE 2-16 2-14 FEB 14 1975

TABLE 2.4.3.-F MAIN STEAM FREQUENCY TYPE OF ACTIVITY OR ANA'LYSIS SENSITIVITY sleekly (6)

(7)

Particulate T 1/2 '>8 days (1)

(4)

Iodine 131 (4)

Estimate steam release rates from sources such as safety

valves, hogging jets, and

-water box priming jets Note (3)

Note (2)

Calculate and Record SEE NOTES ON PAGE 2-1 6 2-15

FEB 14

]gag

NOTES:

(1)

For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations.

Under these circumstances, it will be more appropriate to cal-culate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.

(2)

The sensitivity of the analysis of radioiodines should be sufficient. to permit measurement of a small fraction of the activity which would result in annual exposures of 15 millirems to the thyroid of individuals in unrestricted areas.

(3)

The sensitivity of analysis for radioactive material in particulate form should be sufficient to permit measure-ment, of a small fraction of the activity which would result in annual exposures of 15 millirems to any organ of an individual in an unrestricted area.

(4)

When quantities of released radioactive materials are at low levels, precluding accurate measurement of principal radionuclides, gross radioactivity measurements should be made as a basis for estimating the quantity of radio-active material released.

I (5)

When continuous monitor is inoperable, daily grab samples may be substituted.

(6)

Required only when activity is detected in the Steam Generators by Routine Gross Activity or I-131 Equivalent Analysis.

(7)

Applies during Power operation only.

(8)

Applies only when spent fuel is in the pool.

FEB 14 li(5

Gaseous Release Limits Bases Specifications 2.4.3 provide reasonable assurance that the resulting annual exposure to the whole body or any organ of an individual from gaseous effluents will not exceed 5 millirems/year.

The licensee is permitted the flexibilityof operation compatible with considerations of health and safety, to assure that the public is pro-

.vided a dependable source of power'under unusal operating conditions but still'remain within the limits specified in 10CFR20.

At the same time it is expected that, in using this operational flexibili.'ty under unusual 'operating conditions, the licensee shall exert every effort to keep levels of radioactive material in gaseous wastes as low as practicable and therefore that annual releases will not exceed a small fraction of the annual average concentration limits for unrestricted areas specified in'10CFR20.

These efforts shall include consideration of meteorological conditions during releases.

The potential annual exposures at;the,limiting site boundary concentrations listed, generated from an array of nuclear-electric sites separated a minimum of 50 kilometers radially on eight compass points, would not exceed 5 mrems to the whole body or to the thyroid of individuals remaining off-site.

The design and operation of the equipment for collection and storage of, gases assures capability for holdup for

.activity decay and control of activity released past the plant vent monitor..

Sampling will provide the bases for determination of release rates and valve closure will be initiated if the monitor set point is exceeded, and valve opening is interlocked to Auxiliary Building exhaust fan operation for. initial discharge dilution.,

The release rate limit of 7 millicures per second is based on a maximum annual average site boundary X/Q of 1.73 x 10 6 seconds per cubic meter which was derived for the 5100 foot distance to the northeast site boundary.

After holdup in the gas decay tanks, the predominant nuclide remaining is expected to be Xe-133 which has a Part 20 concentration limit of 3 x 10 7 uc/cc for unrestricted areas.'he'nnual average release rate of 7 millicures per second would result in an annual average concentration't the'orth site boundary of about 4% of the Part 20 limits.

2-1 7 FEB 14 19<5

The specified release rates of I-131 and particulates with half lives greater than eight days would limit concentrations at the nearest "ite'boundary to values of about 1.0% of the limits in Part 20, Appendix B, Table II, Column 1.

The release rate limit of 122 millicures per second averaged over any one hour is a calculated value which would result in an exposure of 2 millirem in that hour assuming inversion conditions.

Meteorolo-gical conditions at the site are expected to be better than these assumed conditions at least 95% of the time.

The limit of 73,000 curies of Xe-133 equivalent in any one gas decay tank is based on a maximum exposure of 0.3 rem due to accidental release of the tank contents under inversion meteorological conditions.

The value of X/Q used for inversion conditions was 8.55 x 10 5 seconds per cubic meter, and the equation in.Safety Guide No.

4 was used to calculate the resulting dose.

E for Xe-133 is 0.19 MEV/disintegration.

D = 0.25 CE X/Q = 0.25 x 73,000 x 0.19 x 8.55 x 10

=0.3 2-3. 8 FEB 14 1975

2.4.5 (Reserved) 2.4.6 Effluent Monitors 2.4.6.1 Li uid Radwaste.Monitor S ecification A liquid radwaste monitor shall be operable during releases

.and set to alarm and automatically ter-minate a release to assure that applicable limits of 10 CFR 20 are not exceeded.

Surveillance (A)

"Channel Functional Test of Monitor

response, alarm and initiation of valve closure Prior to each release (B)

Channel calibration using a known" liquid radioactive solution of expected energies

See 2.4.6.7 Annually 2.4.6.2 Gaseous Radwaste Monitor S ecification A gaseous radwaste monitor shall be operable during releases and set to alarm and automati-cally terminate a release from the Gas Decay Tanks to assure that applicable limits of 10 CFR 20 are not exceeded.

Surveillance Fre uenc (A)

Channel Functional Test of Monitor response alarm and initiation of valve closure Prior to each release (B)

Channel Calibration using known*

radioactive sources of expected energies

See 2.4.6.7 Annually 2-19 FEB 14 19i5

2.4.6.3 Plant Vent Monitor**

S ecification All radioactive wastes discharged through the plant vent shall be continuously monitored for gaseous'ctivity and sampled for Iodine and particulates per table 2.4.2-B.

Surveillance (A)

Channel Check (Qualitative assessment of Channel behavior during operation by observation)

Fre uenc Daily (B)

Channel Functional Test of Monitor

Response

and alarm Monthly (C)

Channel Calibration using known*

radioactive sources of expected energies Refueling

See 2.4.6.7

- See 2.4.6.8 2.4.6.4 S ent -Fuel Stora e Area Monitor**

All gaseous radioactive wastes discharged from the Spent Fuel storage area shall be monitored contin-uously for gaseous activity and sampled for Iodine and particulates per table 2.4.2-E, when spent fuel is in the pool.

Surveillance Fre uenc (A) 'hannel Check (Qualitative assessment of Channel behavior during operation by observation)

(B)

Channel Functional Test of Monitor

Response

and alarm (C)

Channel Calibration using known*

radioactive sources of expected energies Daily Monthly Refueling

See 2.4.6.7

- See 2.4.6.8 2-20 FEB 14 1975

2.4.6.5 Condenser Air E'ector Vent**

S ecification The Condenser Air Ejector Vent shall be monitored continuously for gases,.during power operation; Surveillance Fre uenc (A)

Channel Check (Qualitative assessment of Channel behavior during operation by observation)

(B)

Channel Functional Test of Monitor

Response

and alarm Daily Monthly (C)

Channel Calibration using known*

radioactive sources of expected energies Refueling

See 2.4.6.7

- See 2.4.6.8 2.4.6.6, Steam Generator Blowdown Monitors**

S ecification The Steam Generator Blowdown shall be monitored continuously for gross activity when blowdown is being sent directly to the circulating water system and the monitor set to automatically stop blowdown or divert to the steam generator blowdown treatment facility on preset activity.

Surveillance (A)

Channel Check (Qualitative assessment of Channel behavior during operation by observation)

(B)

Channel Functional Test of Monitor

Response

and alarm (C)

Channel Calibration using.known*

radioactive sou'rces of expected energies Fre uenc Daily Monthly Refueling

See 2.4.6.7

~

- See 2.4.6.8 FEB 14 1975

Process Monitor Calibration The calibration of continuous gross radio-activity monitoring systems should be per-formed by normalizing against the results of specific radionuclide analyses using established ratios of the respective radio-nuclides to total activity.

When calibrated in this fashion, the gross, radioactivity measurements obtained from continuous monitors may be used to determine the total quantity of radioactivity released.

Process Monitor Ino erabilit When a continuous monitor is inoperable, daily grab samples may be substituted.

2-22

2.4.7 Containerized Wastes Containers of radioactive waste materials shall be shipped from the site by licensed carriers in con-formance with the Code of Federal Regulations.

Provisions should be made to monitor the curie

quantity, and to limit the radiation level of each package of solid waste ~in order to reduce radiation exposure to personnel and to meet the regulatory requirements of 10 CFR Part 71, "Packaging of Radioactive Material under Certain Conditions,"

and of the Department of Transporta-tion.

Monitoring of solid wastes in storage and

.preparatory to shipment should be performed to provide assurance that the radiation levels from, waste in storage and in transport do not exceed regulatory limits.

2-23 FEB 14 19i5

3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Non-radiolo ical Surveillance

3. 1.A ABIOTIC 3.1.A.1 Biocides Ob'ective The purpose of this surveillance is to monitor Total Residual Chlorine and Free Available Chlorine in the discharge canal to insure that no adverse impact on the environment is occurring.

S ecification Total Residual Chlorine and Free Available Chlorine shall be monitored near the terminus of the discharge canal on a weekly basis while a condenser section is being chlorinated.

Re ortin Re uirement Total Residual and Free Available Chlorine concen-trations shall be reported in the Annual Environmen-tal Operating Report.

Ob'ective The purpose of this study is to monitor heavy metals concentrations in the intake canal near the sub-aqueous intake pipe, and near the terminus of the discharge canal to detect any measurable increase in heavy metals.

S ecification Grab samples shall be taken on a monthly basis at the intake canal near the subaqueous intake pipe, and near the terminus of the discharge

canal, and analyzed for Mercury, Arsenic, Chromium, Copper, Iron, Lead, Nickel, Selenium, and Zinc.

Re ortin Re uirement Concentrations shall be reported in the Annual Environmental Operating Report.

3-1

3.1.A. 3 pH Ob'ective The purpose of this surveillance is to monitor pH in the receiving waters to insure that pH is not being raised or lowered from the specified limits, in order to prevent, an adverse environmental impact.

S ecification pH shall be monitored daily using grab samples or a recorder near the terminus of the discharge canal.

Re ortin Re uirements 3.1.A.4 pH measurements shall be reported in the Annual Environmental Operating Report.

Dissolved Ox en Ob'ective The purpose of this surveillance is to monitor dissolved oxygen (DO).

S ecification DO shall be monitored weekly, using grab samples, at the intake canal near the subaqueous intake

pipe, and near the terminus of the discharge canal.

Re ortin Re uirements Concentrations shall be reported in the Annual Environmental Report.

~Salinit Ob'ective The purpose of this specification is to measure salinity concentrations in receiving waters.

S ecification Salinity shall be monitored by grab samples on a weekly basis 'near the terminus of the discharge canal.

3-2 FEB 14 19i5

Re ortin Re uirements Salinity concentrations shall be reported in the Annual Environmental Operating Report.

Ob'ective To provide temperature data to limit thermal stress to the aquatic ecosystem.

S ecification Mid-'depth temperatures shall be monitored near the terminus of the discharge canal using a con-tinuous temperature monitoring system.

Temperatures shall be transmitted to the control room and recorded.

Re ortin Re uirement Both intake and discharge temperatures shall be summarized in the Annaul Environmental Operating Report.

3.1.B BIOTIC Ob'ective To determine the effects of plant operation on the planktonic, nektonic, and benthic populations of the Atlantic Ocean near the discharge during plant operation.

S ecification The biological conditions shall be assessed, l) in terms of abundance and compositions of the marine biotic community, and

2) the relationship between certain chemical and physical properties of the waters and the character of the biological community.

The five sampling locations established during a

pre-operational baseline biology program will be utilized for plankton, trawl, and benthic collec-tions.

The sampling schedule will be as follows:

collected monthly and inventoried as to type and abundance of major taxonomic groups present.

3-3 FEB 14 13i5

b)

Plankton Plankton samples will be collected monthly.

Both zooplankton and phytoplankton species will be identified as to kind and abundance.

Chlorophyll "a" analysis will be performed as a measure of primary productivity.

c)

Nektonic Or anisms Samples will be collected monthly by trawl>.ng, seining, or other suitable method.

Types and numbers of organisms present will be determined, including species of migra-tory fish of commercial and sports fisheries value such as blue fish and mackerel.

will be collected quarterly and identified as to species and abundance.

~Q samples taken at bottom, mid-depth, and surface levels at the same time as the biotic samples are collected.

Parameters studied will be temperature, salinity, dissolved oxygen content, turbidity, and selected nutrients.

f)

Mi rator Sea Turtles The species,

numbers, and nesting characteristics of sea turtles that migrate in from the sea and nest along the east coast of Florida will be determined on the FPL shoreline property, and selected adjacent control areas in 1975 and 1977.

':In addition, control studies on temperature

stress, hatching, and rearing factors will be conducted using turtle eggs from displaced nests.

Based on the data obtained, predictions will be made on the impact of the.plant's operation on baseline biological conditions and current, uses of the waters.

Florida Power 6 Light will review the data after two year of plant operation and, if no adverse effects attributable to the plant are definable, the program shall be terminated.

II Re ortin Re uirement Results of the biological program shall be reported in the Annual Environmental Operating Report.

3-4 FEB 14

)S75

3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING will assure cognizance of changes in radioactivity in the environs.

Specification Environmental samples shall be collected and analyzed according to Table 3.2-1.

Bases The environmental monitoring program is desrgned to determine existing radioactivity levels and to detect changes in radiation levels in the air, water or land environment which may be attri-buted to the operation of the unit.

The methods, procedures and techniques developed during the pre-operational phase will be utilized to provide back-ground measurements as a basis for distinguishing significant changes in radioactivity in the site environs.

The environmental monitoring program sample collec-tion frequency and analysis is summarized in Table 3.2.-1.

Table 3.2-2 shows practical reporting limits, and Table 3.2-3 shows types of analyses.

This schedule is designed to ensure that changes in the environmental radioactivity can be detected.

-A continuing review and evaluation of the program will verify the suita-bility and adequacy of the environmental program.

3-5 FEB 14 1975

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soP g SAMtUNO LOCATIONS IJt

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,Ro %El 0 OPERATIONAL RADIOLOGICAL SURVEILLANCE SIQPLING STATIONS Fig.

3. 2-l 3-6

~

FfB 14 19T5

TABLE 3.2-1 SHEET 1 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM l.

AIR Collection Anal sis/Countin 1.1 Particulate and Iodine Comparison on-site versus off-site 6 refererce locations 3 locations on-site, north, east, a southeast of the plant H 34,

H14, H 33 (6) 6 locations off-site within a radius of 10 miles of plant H 08, H 09' lOJ H 12' 30' 32 Weekly Gross Beta Gamma spectral analysis of monthly composit if indicated. by high beta activity (5)

Radioactive Iodine 1.2 Direct Radiation Comparison of on-site versus off-site 6 reference locations 3 locations on-site, north, east,

,6 southeast of the plant H 34, H 14, H 33 (6) 6 locations off-site within a radius of 10 miles of plant H 08',

H 09' 10@

H 12' 30 H 32 Monthly Determine direct radiation by exposure by TLD readout (mean of 2 TLDs) 1.3 Precipitation (3)

Comparison of on-site versus off-site reference locations 1 location on-site, site meteor-ological tower, H 34 3 locations off-site H 08, H 10, H 32 Monthly Gross Beta Gamma spectral analysis 94)

Tritium (4) 2.

WATER 2.1 Surface Water 2.1. 1 Discharge Canal 1 location, east of A1A, H 35 1 location, west of AlA, H 36 Monthly Gamma spectral analysis Tritium Sr-89 6 90 2.1.2 Ocean 5 locations, H 15, H 16, H 17, H18, H19 Quarterly Gamma.spectral analysis Tritium Sr-89 6 90 (if detected in discharge canal)

TABLE 3.2-1 SHEET 2

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM Collection Anal sis/Counting 2.

WATER (cent'd) 2.1.3 Intake Canal 1 location, H 37, east of AlA at beginning of open canal Quarterly Gamma spectral analysis Tritium Sr-89 6 90 (if detected in discharge canal) 2.1.4 Estuarine 1 location, Big Mud Creek, H 13 Quarterly Gamma spectral analysis Tritium Sr-89 a 90- (if detected in discharge canal) 2.1.5 River (fresh water) 1 location, St. Lucie River at US 1, H 29, Quarterly Gross Beta Tritium 2.1.6 Inland (fresh water) 1 location, Walton Road 6 Marsh, H 27 1 location, Weatherbee Road 6

Marsh, H 28 Semi-annually Gross Beta Tritium 2.2 Ground Water (wells) 1 location, Residence, 7609 Indian River Drive, H 30 Semi-annually Gross Beta Tritium 2.3 Potable Water (wells) 1 location, City of Ft. Pierce, drinking water supply, H ll 1 location, City of Stuart, drinking water supply, H 12 1 location, Port St. Lucie, drinking water supply, H 31 Quarterly Gamma spectral analysis Gross Beta Tritium 3.

BOTTOM SEDIMENT 3.1 Discharge Canal 1 location, east of AlA, H 35 1 location, west of AlA, H 36 Quarterly Gamma spectral analysis Sr-89 6 90

TABLE 3.2-1 SHEET 3 OPERATIONAL'NVIRONMENTALRADIOLOGICAL SURVEILLANCE PROGRAM Collection Anal sis/Countin 3.

BOTTOM SEDIMENT (cont'd) 3.2 Ocean 1 locaticn, mouth of discharge structure, H 15 1 location, offshore, 1 mile north of discharge, H 16 1 location, offshore, 1 mile south of discharge, H 19 Semi-annually Gamma spectral analysis Sr-89

& 90 (if detected in discharge canal sediment) 3.3 Beach (sand) 1 location, Plantom Beach, opposite discharge, H 33 1 location, east of Blind Creek, 1

mile north of discharge, H 16 1 location, near intake, 1 mile south of discharge, H 19 Quarterly Gamma spectral analysis Sr-89

& 90 (if detected in discharge canal sediment) 3.4 Estuarine 1 location, Big Mud Creek, H 13 Semi-annually Gamma spectral analysis Sr-89

& 90 (if detected in discharge canal sediment) 4.1 Crustacea Lobster or crab or shrimp 4 locations, H 17, H 18, H 20, H 21 1 location, discharge canal, west of AlA, H 36 Semi-annually Quarterly Gamma spectral analysis Sr-89

& 90 Gamma spectral analysis Sr-89

& 90 4 '

Fish

4. 2.1 4 ~ 2.2 Carnivores (Mangrove Snapper)

Herbivors (Mullett) 4 locations, H 17, H 18, H 20, H 21 Semi-annually 4 locations, H 17, H 18, H 20, H 21 Semi-annually Gamma spectral analysis Sr 89

& 90 Gamma spectral analysis Sr-89

& 90

TABLE 3.2-1 SHEET 4 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM Collection Anal sis/Countin Bl'"'cont'd) 4.2.2 Herbivors (Mullett) 5.

TERRESTRIAL 1 location, discharge

canal, west of AlA, H 36 Quarterly Gamma spectral analysis Sr-89 6 90

5. 1 Milk 1 location within 15 mile radius of plant and in the prevailing wind direction from the plant;,H 01 1 location, Florida (state)'ilk Shed Montnly Gamma spectral analysis Sr-89 6 90 1-131

5. 2 Biota 5.2.1 Food Crop (Citrus) 6 locations, H 10, H 22, H 23, H 24, H25, H26 Harvest Time Gamma spectral analysis Sr-89 s 90 5.2.2 Other Vegetation 5 locations within a 10 miles radius of plant, H 08, H 09, H 10, H 27, H 28 Semi-annually Gamma spectral analysis Sr-89 6 90 5.3 Soil 5 locations within a 10 mile radius of plant, H08, H09, H10, H27, H 28 Semi-annually Gamma spectral analysis Sr-89 6 90 (1)

Samples will be taken whenever biologically available.

(2)

Frequency definitions follow:

Weekly.

Not Monthly-Not Quarterly

Not Semi-annually-Not less than 48 times per annum Interval may vary by 3 days.

less than 10 times per annum Interval may vary by 15 days.

less than 4 times per annum Interval may vary be 30 days.

less than 2 times per annum Interval may vary by 60 days.

l'

TABLE 3.2-1 SHEET 5

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM (3)

Analysis will be performed provided sufficient wet deposition occurs.

(4)

Gamma spectral and tritium analysis will be performed provided sufficient size liquid sample is collect d.

(5) If mean of gross beta activity of the 9 air samples exceeds lO pCi/cc (lpCi/m3)

(6)

East of AlA 6 plant structures to be installed when construction activity permits.

TABLE 3.2.-2 PRACTICAL REPORTING LIMITS Gamma S ectrosco Nuclide Vegetation and Water 3.5 1 Geometry Soil and Biota 1.0 1 Geometry Cerium 144 Iodine 131 Ruthenium 106 Cesium 137 Cesium 134 Cobalt 58 Cobalt 60 Zirconium 95 Manganese 54 Zinc 65 Potassium 40 Barium 140 Radium 226 Thorium 232 9.7 x 1-7 x 8.3 x le7 x 1.7 x 1

7 x 107 x 1.4 x 1.4 x 3+i x 1.8 x 1.7 x 5.7 x 2.8 x

'10-8 10-8 10-8 10-8 10-8 10-8 10-8 10-8 10-8 10-8 10 10-8 10-8 10-8 pCi/ml PCi/ml pCi/ml pCi/ml pCi/ml pci/ml pCi/ml PCi/ml PCi/ml pCi/ml PCi/ml pCi/ml PCi/ml pCi/ml 2.0 x 10 4.0 x 10 1.8 x 10 4

0 x 10-8 6

0 x 10-8 6.0 x 10 8

6-0 x 10-8 3.0 x 10 3.0 x 10-8 7.0 x 10-8 3.9 x 10 4.0 x 10 2.0 x 10 1.0 x 10 PCi/ml PCi/ml PCi/ml

'PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml PCi/ml Other Anal ses Strontium 90 Tritium Gross Alpha (water)

Gross Alpha (ash)

Gross Beta (water)

Gross Beta (ash)

Gross Beta air particulate filters (Based on a total Air Iodine Cartridges 8.0 2.0 7

7 3

1 7.7 flow of 7.7 pCi/gm ash x 10 pCi/ml (1 liter sample) x 10 pCi/ml (1 liter sample) x 10 6 pCi/gm ash x 10 9 pCi/ml (1 liter sample) x 10 5 pCi/gm ash x 10-12 PCi/cc 2200 m3) x 10 PCi/cc 3-12

TABLE 3 ~ 2 3

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM TYPE OF ANALYSIS 1.

Gamma S ectrosco Ce-144 I-131 Ru-106 Cs-134 Cs-137 Zr-95 Mn-54 Zn-65 Ba-140 K-40 Ra-226 Th-232 Co-58 Co-60 Cr-51 2.

Beta Li uid Scintillation S ectrosco H-3 C-14 P-32 3.

Chemical Se aration and Anal sis Sr-89 Sr-90 3-13 FEB 14 ]9(5

4.0 SPECIAL SURVEILLANCE AND SPECIAL STUDY ACTIVITIES 4.1

. Im in ement of Or anisms Ob'ective The purpose of this study is to monitor those fish impinged on the intake traveling screens to permit a quantitative and qualitative assessment of the impingement.

S ecification The total weight and number of fish, by species, removed from the traveling screens shall be monitored Monitoring will be done during normal operations using a continuous collection period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months every two weeks.

The study shall be terminated two years after commencing plant operations.

Re ortin Re uirements Results of this study shall be summarized in the Annual Environmental Report.

4.2 Land Mana ement Transmission line right-of-way through the Savannas will be virtually undisturbed after the initial installation.

The natural vegetation and water flow will remain the same.

Potential erosion of the right-of-way is not expected.

The plant site will be landscaped after consultation with a landscape architect.

Grasses indigenous to the area will be planted to prevent erosion in the intake and discharge canal area.

Further study is being conducted to determine the appropriate types of trees or suitable plants which should be used as a light screen to minimize turtle disorientation.

4-1 FEB 14 l9i'5

5.0 ADMINISTRATIVE CONTROLS The purpose of this section is to describe the administrative and management controls necessary to provide continuing pro-tection to the environment, and to implement the environmental technical specifications (ETS).

5.1 Res onsibilit The Vice President of the Environmental Department has the ultimate responsibility for the implementa-tion of the ETS.

He may delegate to other depart-ments and/or organizations the work of establishing and executing portions of the ETS, but shall retain responsibility thereof.

The Environmental Department is responsible for executing the non-radiological biotic and special studies sections of the ETS.

The Vice President of Power Resources is responsible for executing the non-radiological abiotic, radioactive effluents, and the Radiological Environmental Surveillance sections.

The Plant Quality Control group shall be respon-sible for the day-to-day verification of compliance with the ETS.

The Manager of Quality Assurance shall be responsible for periodic audits, conducted according to the corporate Quality Assurance

program, to insure compliance with the ETS.

5.2 Or anization 5.3 The corporate organization involved in environmental matters is depicted in Figure 5.2-1.

Review and Audit 5.3.1 Review of implementation of the ETS shall be made by the Company Environmental Review Group (CERG) or by the Plant Nuclear Safety Committee (PNSC).

Secondary reviews shall be made by the Company Nuclear Review Board (CNRB).

5.3.2 PNSC and CNRB membership and responsibilities are described in Appendix A, Technical Specifications.

5-3-3 COMPANY ENVIRONMENTAL REVIEW GROUP (CERG)

A.

Function The Company Environmental Review Group (CERG) shall function to advise the 5-1 FEB 14 1976

EXECUTIVE VICE PRESIDENT VICE PRESIDENT ENVIRONMENTAL DEPARTMENT VICE PRESIDENT NUCLEAR AFFAIRS GROUP VICE PRESIDENT COMPANY NUCLEAR REVIEW BOARD COMPANY ENVIRONMENTAL REVIEW GROUP

MANAGER, QUALITY ASSURANCE VICE PRESIDENT POWER RESOURCES MANAGER OF POWER RESOURCES-NUCLEAR PLANT MANAGER PLANT NUCLEAR SAFETY COMMITTEE FLORIDA POWER 6 LIGHT COMPANY CORPORATE ORGANIZATION ENVIRONMENTAL AFFAIRS FIGURE 5.2-1 AUTHORITY

COMMUNICATION

Vice President,'nvironmental Department on all matters related to environmental quality.

B.

Membership 1.

Manager, Environmental Engineering Chairman 2.

Manager, Environmental Affairs 3.

Senior Environmental Engineer, Environmental Engineering 4.

Power Resources Test Group Supervisor 5.

Environmental Department Biologist 6.

Environmental Department Senior Project Coordinator 7.

Plant supervisor (Plant Involved) 8.

Power Resources Administrative Assistant Nuclear C.

Alternates Alternate members shall be appointed in writing by the CERG Chairman.

No more than two alternates shall participate in CERG activities at any one time.

D.

Meetin Fre uenc The CERG shall meet at least semiannually and as convened by the CERG Chairman or designated acting Chairman.

E.

Quorum A quorum of the CERG shall consist of the Chairman, or designated acting Chairman and three members including alternates.

F.

Res onsibilities 1.

Review of all Environmental Depart-ment procedures required by Environ-mental Technical Specifications and changes thereto.

Review of any pro-posed procedures or changes thereto as determined by the Plant Manager to affect the environment.

2.

Review results of the environmental monitoring programs prior to their submittal to the NRC.

3.

Review of all proposed test and experiments as determined by the Plant Manager to affect the environment.

5-3

4.

Review of all proposed changes to the Environmental Technical Specifications.

5.

Review of all proposed changes or modifications to plant systems or equipment as determined by the Plant Manager to affect the environment.

6.

Review of investigation of violations of the Environmental Technical Speci-fications.

7.

Performance of special reviews and investigations and reports thereon as required by the Chairman of the Company Nuclear Review Board.

The Company Environmental Review Group shall:

- Recommend to the Vice President, Environmental Department, written approval or disapproval of the items considered under F.l through F.5'above.

H.

Records The Company Environmental Review Group shall maintain written minutes of each meeting and copies shall be provided to the Vice President, Environmental Depart-ment, Vice President, Power Resources, and the Chairman of the Company Nuclear Review Board.

5.3.4 Periodic audits concerning the implementation of the ETS shall be made as provided in the Quality Assurance Manual.

5.4 Action To Be Taken If A Limitin Condition Is Exceeded 5.4.1 When a Limiting Condition is exceeded, action shall be taken as permitted by the applicable specification until the condition can be met.

5.4.2 Exceeding a Limiting Condition shall be in-vestigated by the Company Environmental Review Group or by the Plant Nuclear Safety Committee.

5. 4.3 All reviews and actions taken, with reasons therefore, shall be recorded and maintained as part of the permanent records.

FE8 14 19i5

5.4.4 Each instance whereby a Limiting Condition is exceeded shall be reported to the Company Nuclear Review Board.

5.4.5 A report for each occurrence shall be pre-pared as specified in Section 5.6.2.

5.5 Procedures Detailed written procedures, including appli-cable check lists and instructions, shall be prepared and followed for activities involved in carrying out the environmental technical specifications.

Procedures shall include

sampling, data recording and storage, instru-ment calibration, measurements and analyses, and actions to be taken when limits are exceeded.

Testing frequency of any alarms shall be included.

5.5.2 Plant operating procedures shall include provisions to ensure that, plant systems and components are operated in compliance with the environmental technical specifications.

5.6 Re ortin Re uirements 5.6.1 Routine Re orts Annual Environmental 0 eratin Re ort A report on the environmental surveillance programs for the previous 12 months of operation shall be submitted to the Direc-tor of the Regional Office of Inspection and Enforcement with a copy to the Direc-tor of the Office of Inspection and En-forcement 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 evaluation of the results of the environ-mental monitoring programs required by limiting conditions for operation 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 or irre-versible 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.

5-5 FEB 1 i 1

~ ~

0

A report on the radioactive discharges released from the site during the pre-vious 12 months of operation shall include the following:

Analyses of Effluent releases from sections 2.4.1 and 2.4.3 shall be sum-marized on a quarterly basis and re-ported on the format similar to Table 5.6.1-A, B, C, 6 D.

Supplemental information shall be included covering topics similar to those itemized in Data Sheet 5.6.1-1.

Abnormal.releases should be handled as batch releases for accounting purposes and also reported as shown on Data Sheet 5.6.1-1 according to 5.6.2.

Solid wastes shall be summarized on a quarterly basis and reported in a for-mat similar to that of Table 5.6.2-E.

The following information should be reported for shipments of solid waste and irradiated fuel transported from the site during the report period.

1.

The annual total quantity in cubic meters and the annual total radioactivity in curies for the categories or types of waste.

a ~

b.

c ~

d.

Spent resins, filter sludges, evaporator bottoms; Dry compressible

waste, con-taminated equipment, etc.;

Irradiated components, control rods, etc.;

Other (furnish description).

2.

An estimate of the total activity in the categories of waste in 1) above.

.3

~

The disposition of solid waste shipments.

(Identify the number of shipments, the mode of transport, and the destination).

4.

The disposition of irradiated fuel

'hipments.

(Identify the number of shipments, the mode of transport, and the destination).

. 5-6 FEB 14 i

~ 5

DATA SHEET 5.6.1-1 EFFLUENT AND WASTE DISPOSAL Supplemental Information Facility License 1.

Regulatory Limits

'a ~

b.

c d.

Fission and activation gases:

Iodines:

Particulates, half-lives

>8.days:

Liquid effluents:

2.

Maximum Permissible Concentrations Provide the MPCs used'n determining allowable release or concentrations.

a ~

b.

C ~

d.

Fission and activation gases:

Iodines:

Particulates, half-lives

>8 days:

Liquid effluents:

3.

Average Energy Provide the average(E)of the radionuclide mixture in releases of fission and activation gases, if applicable.

4.

Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

a b.

c ~

d.

Fission and activation gases:

Iodines:

Particulates:

Liquide effluents:

5.

Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

5-7 FEB 1 1

a.

Liquid 1.

Number of batch releases:

2.

Total time period or batch releases:

3.

Maximum time period for a batch release:

4.

Average time period for batch releases:

5.

Minimum time period for a batch release:

6..

Average stream flow during periods of release of effluent into a flowing stream:

b.

Gaseous l.

2.

3.

4

~

5.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for 'batch releases:

Minimum time period for a batch release:

6.

Abnormal Releases a.

Liquid 1.

Number of releases:

2. 'otal activity released:

b.

Gaseous 1.

Number of releases:

2.

Total activity released:

5-8 FEB14 iJ:i

TABLE 5.6.1-A GASEOUS EFFLUENTS-SUMPTION OF ALL RELEASES Unit Quarter Quarter A.

Fission 6 activation gases

l. Total release 2.

Average release rate for period 3.

Percent of Technical specification limit pCi/sec E

E E

E B.

Iodines 1.

Total iodine-131 Ci E

E 2.

Average release rate for period 3.

Percent of Technical specification limit pCi/sec E

E E

E C.

Particulates 1.

Particulates with half-lives 8 days 2.

Average release rate for period 3.

Percent of echnical specification limit 4.,Gross alpha radioactivity Ci pCi/sec Ci E

E E

E D.

Tritium l.

Kbtal release 2.

Average release rate for period 3.

Percent of Technical specification limit pCi/sec E

E E

E 5-9 FEB 14

TABLE 5.6.1-B Nuclides Released 1.

Fission gases GASEOUS EFFLUENTS CONZIMXXJS IKGE BATCH MODE kr ton-'85 kr ton-85m kr ton-87 kr ton-88 xenon-133 xenon-135 xenon-135m xenon-138 Others (s ecif

)

unidentified Total for eriod 2.-

Iodines iodine-131 iodine-133 iodine-135 Total for eriod 3.

Particulates Ci Ci E

E E

E strontium-89 strontium-9C cesium-134 cesium-137 barium-lanthanum-140 Others (s ecif

)

unidentified Ci Ci Ci E

E E

E 5-10

TABLE 5.6.1-..C LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter A.

Fissions'and"activation products 1.

Total release (not secluding trz.thun, ases, al ha) 2.

Average diluted concentration dur3.ng perl.od 3.

Percent of applicable limit Ci pci/ml E

E E

E B.

Tritium 1.

Total release 2.

Average diluted concentration dur1I1 iod 3.

Percent of applicable limit Ci pC1/ml E

E E

E C.

Dissolved and entrained gases 1.

Total release Ci E

E 2.

Average Chluted concentration duX3J1 iod 3.

Percent of applicable limit D.

Gross alpha radioactivity uCi/ml E

E E

E l.

Total release Ci E

E E

E F.

Volune of dilution water used during period liters E

E 5-11

TABLE 5.6.1-D LIQUID EFFLUENTS Nuclxdes Released strontxmn-89 strong.um-90 cesium-134 cesiun-137 iodine-131 CDNZIKDUS K)DE E

E E

'E E

E E

Quarter E

E E

cobalt-58 cobalt-60 iron-59 zinc-59 manganese-54 chranium-51 Ci E

E E

ziroanien-ruo um-95 moly ernxn-99 technetium-99m barium-lanthanum-140 cerium-141 Ci E

E E

E Other (specify)

Ci Ci E

E E

E xenon-133 xenarr E

E E

E

~ E E

TABLE 5.6.1-E SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL(Not irradiated fuel) 1 PUB of waste a.

Spent rests, filter sludges, evaporator

bottoms, etc.'.

Dzjj compressible waste, contanu.nated etc.

c.

Irradiated ccmponents, control rods etc.

d.

Other (describe)

Unit m

Ci mCi m3 Ci 6-anth Period E

E E

E 2.

SOLID RESTE DISPOSITION Number of Shi ts Hade of Trans rtation Destination B.

-IRRADIATED FUEL SHIPMENTS (Disposition)

Nunber of Shi ts l4xh of Transportation Destination 5-13

5. 6. 2 Non Routine Re orts A report shall be submitted in the event that:

(a) a limiting condition is ex-ceeded (as specified in Section 2.0 Limiting Conditions), or an unusual or important event occurs that causes a

significant environmental impact, that affects potential environmental impact from plant operation, or that has high public or potential public interest con-cerning environmental impact from plant operation.

Reports shall be submitted under one of the report schedules des-cribed below.

(1)

Prompt Reports II Those events requiring prompt reports shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission to the Director of the Regional Office of Inspection and Enforcement and within 10 days by a written report to the Director of the Office of Inspection and Enforcement.

(2) 30-Day Reports Those events not requiring prompt reports shall be reported within 30 days by a written report to the Director of the Regional Office of Inspection and Enforcement with a copy to the Director of the Office of In-spection and Enforcement.

The reporting schedule for reports concerning limiting conditions shall be reported on the 30-Day schedule.

Reports concerning unusual or important events shall be reported on the prompt schedule.

Written 10-day and 30-day reports and to the extent possible the preliminary telephone, telegraph, or facsimile reports shall:

(a) describe,

analyze, and evaluate the occurrence, including extent, and magnitude of the impact, (b) describe the cause of the occurrence and (c) indicate the correc-tive action (including any significant changes made in procedures) taken to preclude 5-14

repetition of the occurrence and to prevent similar occurrences involving similar com-ponents or systems.

The significance of an unusual or apparently important event with regard to environmental impact may not be obvious or fully appre-ciated at the time of occurrence.

In such

cases, the NRC shall be informed promptly of changes in the assessment of the signifi-cance of the event and a corrected report shall be submitted as expeditiously as possible.

5.6.3 Chan es in Environmental Technical S ecifications Request for changes in environmental technical specifications shall be sub-mitted to the Director of Nuclear Reactor Regulation for review and authorization.

The request shall include an 'evaluation of the environmental impact of the pro-posed change.

5.7 Records Retention 5.7.l Records and logs relative to the following areas shall be made and retained for the life of the plant:

a ~

b.

Records and drawings detailing plant design changes and modifications made to systems and equipment as described in 5.3.3.F.S.

Records of all environmental surveillance data.

c.

Records to demonstrate compliance with the limiting conditions in Section 2.

5.7.2 All other records and logs relating to the environmental technical specifications shall be retained for five years following logging or recording.

These shall include (but are not limited to) the following:

a.

Details or any abnormal operating conditions having an effect on the environment, and actions taken to correct those conditions.

b.

Maintenance activities to environment monitoring equipment, including but not limited to:

(1) routine maintenance and component replacement, (2) equipment failures, (3) replacement of principal items of equipment.

c.

Records of radioactivity levels in liquid and gaseous wastes released to the environment.

A d.

All reviews, including actions take and reasons therefore, required in Sections 2,

3, and 4 of this specification.

5-16

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