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FMRIDA POLiER 6 LIQlT COoPALLST. LUCIE PLANT

C1lF"HSTF.Y DHPART'ENTIETTER OF INSTRUCTION CC-04 REVISION 0

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OF .II"1~02c Rr.CIRCIfLPTIO".TDES FOR RZPP" SEXTATIVE

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Rcvicved by P

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Date to bc Re

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>liIS tO Jl'.<LLEW IS HOT CONfSI.tt0 V(5R:USf'CLf.!IIPt'iiaLOLI«ihll9NVL'lrLI A CQ!I"IPO.'ffn

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in Table I have creen~ v

3.0 'Purpose "nd Disc u..sion: ~ ~

5~ J. To Qstablish .in+'aura recirculation ti~es .or various tan'ks to reachequilibriu~a a'ter che vocal'hanges are made,

3.R To establS.sh nininiu~ times for recirculation fprior to samplingtanks w order to assure representative sanplca. Certain tanksand syste. s have concentration lie=its required by technicalspecificat ons, ex. Boric Acid Haieup Tanks. Also RegulatoryGuide la21 states that large volu=ies of liquid waste should bepiggy in as short a t,i"..e as possible to assure sedi™cnts and

particu3utes are uniiormlp distributed prior to sa=pling.~ ~

4 0 0 IilSCYVCC3.0nS a

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to bc used r )

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through noaaaI recirculation path.4;1.3 Co ~-"ence rccircu at on o

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be der.ernincd dcpcn cnt on

4.1.5 Drain and xc i tan.f II k to wct layup conditions of CC-03

f.f nCCCSSLQryc

Enclos»re l~ ~

LETTER OF IhSTR JCTXO'8 CC 0 l ~ REVISION 0CO~l{'UTATIOa) 01'11.'$l:3:;f. RcC:PC% 'aTION TOMS

kM PKPRESLNTATD'E SAiPLlhC

Pg. 2 of 4

4,0 Instructions: (Cont.)

4.1.6 Ensure all data on log sheet Appendix I Xs filledout and iiled in 1hstcr and Chemistry Department files.

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? ETTER OF ItlSTRUCTIOl) CC-04, r'KVESION 0CO~~ZUTATION OF 'il:lflM'iIUZEI:CULRTIOli TIlKS

VCR RHPPESEliTATEVE Shit'LEUC~ ~

TABLE X

Boric Acid Condensate Tanks~ ~

Vastc Condcnsntc Tan's

CVCS )iold-Up Tanks

Boric Acid iiolding Tank

3A, 19, 1C, lDI

Equip"..ent Drain Tank

Chemical Drain Tank

efg

Laundry Drain Tanks

Refueling Pater Storage Tank

Boric Acid Hakeup Tanks

Aerated Vaste Storage Tank~ 0

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B)R REPOSE'iTATXVE SAiPLXNG.

Pg. 4oE 4

Appendix X

a TANK'R..CIRCU1 ETIO!a DATA 8HZ 7

- TP.ISSE'/ rC a(~? LWSA.F.

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RECKRCULATKO!i FLOP RATE A:2) DZSaa

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TABLE OF CONTENTS

1.0 DEFINITIONS

P acae

1.11.21.31.41.51.61.71.81.91. 10l. 111.121.131.141,151.16

National power emergencyA regional emergencyReactor emergencyCirculating water systemFrequency definitions followTotal Residual ChlorineIntake TemperatureDischarge TemperatureDissolved OxygenLimiting Conditions'SalinityContinuous RecordingChannel CalibrationChannel Functional TestBatch ReleasesContinuous Release

1»11-1l-l1-11-11-21-21-21«21-21-21-21-21»31-31-3

2.0 LIMITING CONDITIONS

General

2-1

2.1

2 ~ 2.

2.4

Thermalr

2..1.1. Maximum Discharge 'Temper'ature'.1.2Maximum Condenser Temperature Rise

Chemical

2.2.1 Biocides2.2.2 pH

Radioactive Effluents

2~2

2~22-3

2-3

2-5

2.4. 12.4.2

2.4.32.4.4

2. 4'.5

Liquid EffluentsLiquid Naste Sampling andMonitoringGaseous Naste EffluentsGaseous Waste Sampling andMonitoringSolid Waste Handling andDisposal

2-.5

2-62«10

2-13

2-16

3.0 ENVIRONMENTAL SURVEILLANCE 3-1

3.1 Non-Radiological Surveillance

3.1.A ABIOTXC

3«1

3-1

3,1,A,13.1.A.23. 1.A. 33. 1.A.4

BiocidesHeavy MetalspHDissolved Oxygen

i

3-13-13-23-2Rev. 4 7/28/75

TABLE OF CONTENTS (Continued)

Pacae

3.1.A.53.1.A.6

3.1.'B BIOTIC

SalinityTemperature

3-23-3

3-4

a) Benthic Organismsb) Planktonc) Nektonic Organismsd) Macrophytese) Water Qualityf) Migratory Sea Turtles

3.2 Radiological Environmental Monitoring3.3 Onsite Meteorological Monitoring

3-43-43-43-43-43-5

3-63-18

4o 0 SPECIAL SURVEILLANCE 6 SPECIAL STUDY ACTIVITIES4-1

4. 1 Entrainment of Aquatic Organisms4.2 Impingement of Aquatic Organisms4.3 Minimum Effective Chlorine Usage

5, 0 ADMINISTRATIVE CONTROLS

5.1 Responsibility5.2 Organization5.3 Review and Audit5.4 Action To Be Takne If A Limiting

Condition Is Exceeded'5.5 Procedures5.6 Reporting Requirements

4-14-14-2

5-1

5-15-15-15»4

5-55-5

5.6.15.6.25.6.3

Routine ReportsNon Routine ReportsChanges in EnvironmentalTechnical Specifications

5-55-145-16

5.7 Records Retention

6.0 SPECIAL CONDITIONS

6.1 Light Screen to Minimize TurtleDisorientation

5-16

6-1

Rev. 4. 7/28/75

TABLE OF CONTENTS (Continued)

TABLES

Table 2.4.1

"Table 2.4.2

Table 2.4.3

Table 2.4.4

Table 2.4.5

Table 3.2-1

Table 3. 2-2

Table 3.2-3t Table5.6.1-1'able

5.6.1-A

Radioactive Liquid Sampling Analysis

Radioactive Gaseous Waste Sampling andAnalysis

'Liquid Waste System — Monitors andSamplers

Gaseous Waste System Monitors andSamplers

Gamma and Beta Dose Factors

Operational EnvironmentalRadiological SurveillanceProgram — Sampling Locations

Operational Environmental RadiologicalSurveillance Program

Detection CapabilitiesEffluent and Waste Disposal

Gaseous Effluents — Summationof All Releases

Pacae

2-17

2-19,

2-20

2-21

2-22

3-9

3-14

3-17

5-7

5-9

Table 5. 6. 1-C Liquid Effluents - Summationof All Releases

Table 5.6.1-D Liquid EffluentsTable 5.6.1-E Solid Waste and Irradiated

Fuel Shipments

Table 5.6.1-B Gaseous Effluents 5-10

5-11

5-12

5-13

Rev. 4 7/28/75

FIGURES

Figure 3.2-1

Figure 3.2-2

TABLE OF CONTENTS (Continued)

Operational RadiologicalSurveillance Sampling Stations

Inset to Figure 3.2-1

Pacae

3-12

3-13

Figure 5. 2-1 FP&L Corporate Organization—Environmental Affairs

5-2

iv Rev 4. 7/28/75

1,6 Total Residual Chlorine

The amount of free and combined available chlorinepresent in water.

1.7 Intake Tem erature

The temperature of the cooling water as measuredat the plant intake structure.

1,8 Dischar e Tem erature

The temperature of the cooling water as measurednear the terminus of the discharge canal.

1.9 Dissolved Oxy en

Oxygen dissolved in the condenser cooling water,and expressed in milligrams per liter,

1.10 Limitin Condition

Those conditions to be imposed on plant effluentsand operating practices which may have an adverseimpact. on the environment.

1. 11 ~Salin it

1,12

The total amount of solid material in gramscontained. in one killogram of sea water whenall the carbonate has been converted to oxide,the bromine and, iodine replaced .by chlorine,and organic. matter completely oxidized.

Continuous Recordin

: Recording of a measured parameter, on a chart; by a single pen or a multipoint recorder with.less than a one-minute interval between successiveprinting of the same parameter.

1.13 Channel CalibrationA Channel Calibration shall be the adjustment ,of the channel output such that it respondswith specified range and accuracy to knownvalues of the parameter which the channelmonitors, The Channel Calibration shallencompass the entire channel including thesensor and alarm and/or trip functions, andshall include the Channel Functional Test.

Rev. 4 7/28/7S

1. 14 Channel Functional Test

A Channel Functional Test shall be the injectionof a simulated signal into the channel as closeto the primary sensor as practicable to verifyOperability including alarm and/or trip functions.

1.15 Batch Releases

Discontinuous release of gaseous or liquid effluentwhich takes place over a finite period of time,usually hours or days.

1,16 Continuous Release

Release of gaseous or liquid effluent which isessentially uninterrupted for extended periodsduring normal operation of the facility.

1-3 Rev. 4 7/28/75

2.1 THERMAL

2.1.1, Maximum Dischar e Tem erature

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

Specification:The thermal discharge of St. Lucie Unit No. 1 into theAtlantic Ocean shall be limited to a maximum of ill'Fand shall not, cause a temperature rise in excess of 1.5'Fabove ambient surface temperature outside a 400 ~ere zoneof mixing during the months of June through September, nora O'F rise during the remaining months. Zn addition, the

.surface temperature conditions within the zone of mixingshall not exceed a rise of 5.5'F over ambient temperaturenor a maximum temperature of 93 F as an instantaneousmaximum at any point.Thermal defouling. of the intake pipeline is allowed subjectto a maximum release temperature of 120'F, and a maximumsur face temperature rise o f 2'F.

Under the following conditions, which may be expected tocause the discharge tempe::ature to be higher than design,the maximum discharqe temperature shall be limited to 115'F:1) Condenser and/or circulating water pump maintenance;2) Throtling circulating water pumps to minimize use ofchlorine; 3) . ouling of circulating water system.

Temporary transients due to accidental loss of c'rculatingwater system components may cause temperature rises in excessof limitations stated above'. Variances due to the. e transientsshall be limited to no more than 7 hours per month.

Monitorin Requirement:

A continuous temperature measurement system shall be installedin the discharge canal at mid-depth. Temperatures shall betransmitted to the control room.'

continuous temperature monitoring station located within500 feet from the pr'mary monitoring device, shall be usedas a backup system if the primary system fails. Xn thisevent this station "hall be checke"'very 8 hours until theprimary system is restored. See section 3.1.A.6 for completedetails of the monitoring program.

2-2. Rev.. 4 7/28/75

2, 1. 2 - Maximum Condenser Tem erature Rise

Bases:

Under normal full power operation, the temperature riseacross the condenser shal'1, not exceed. 26'F. ~ Under thefollowing conditions, the condenser temperature 'riseshall not exceed 35'F: 1) Condenser and/or circulatingwater pump maintenance; 2) Throttling circulating waterpumps to minimize use of chlorine; 3) Fouling ofcirculating water system.

The limitations provide reasonable assurance that the overallaquatic ecosystem in the area of the thermal plume w'illexperience an acceptable environmental impact. The placementof the temperature monitoring instrument in the dischargecanal will give the temperature of the discharge water beforemixing with the receiving water.

2.2 CHEMICAL

~b'he

purpose of these specifications is (1) to minimize impactsto the quality of the, Atlantic Ocean, (2) to protect the localbiota from lethal and sublethal effects of exposure to chemicaldischarge due to operation of the plant, (3) to assure thatcontinued multiple use o the receiving waters by humanpopulations is protected, and (4) to control the quality ofthe receiving medium.

2.2.1 Biocides

otal Residual Chlorine at the downstream end of thedischarge canal shall not exceed o.2 mg/1 on an averagefor a chlorination addition period. If this level isexceeded, adjustments to the injection system shall bemade to reduce the concentration, and each suceedi.'ngchlorination period shall be monitored until the concen-tration is within the specification. Chlorine shall beadded for less than 2 hours per day.

Monitorin Requiremen'ts:

A grab sample of condenser cooling. water shall betaken weekly in the discharge canal and analyzed fortotal residual chlorine. The samples shall be takenduring the period of chlorination. The time of be-ginning the chlorination and when the sample was takenshall be logged.

2-3 Rev. 4 7/28/75

Bases:

~8hen injected, chlorine is diluted by the coolin'gwater and consumed in the process of controllingslime. To be sure that enougn chlorine is injectedto control the slime, the residual chlorine concen-tration will be approximately 1 mg/1 at the condenseroutlet. This concentration corresponds to a concen-tration in the immediate vicinity of the dischargeof less than 0.2 mg/1, The limits set forth providereasonable assurance of an acceptable environmentalimpact.

2.2.2 pH

The pH of the cooling water in the discharge canalshall not be less than 6,0 nor greater than 9.0 pHunits.

P

Monitorin Re uirement:

pH shall be measured on a daily basis in the dischargecanal, and it shall be accomplished using either agrab sample or recorder.

Basis:

The pH limits set forth will provide reasonableassurance of an acceptable environmental impactwhen discharging waters to -the Atlantic Ocean.

2-4 Rev. 4 7/28/75

2.4 RADZOACTXVE EFFLUENTS

Ob'ective

To define the limits and conditions for the controlledrelease of radioactive materials in liquid and gaseouseffluents to the environs to ensure that these releasesare as low as practicable. These releases should notresult in radiation exposures in unrestricted areasgreater than a few percent of natural background exposures.The concentration of radioactive materials in effluentsshall be within the limits specified in 10 CFR Part 20.

To ensure that the releases of radioactive material abovebackground to unrestricted areas be as low as practicableas defined in Appendix I to 10 CFR Part 50, the followingdesign objectives apply:For liquid wastes:

a. The annual dose above background to the total body orany organ of an individual from all reactors at a siteshould not exceed 5 mrem in an unrestricted area.

b. The annual total quantity of radioactive materials inliquid waste, excluding tritium and dissolved gases,.discharged from each, reactor should not exceed 5 Ci.

For gaseous wastes:

c. The annual total quantity of noble gases above back-ground discharged from the site should result in an,annual air dose .due to gamma radiation of less than10 mrad; and an annual air dose due to beta radia-tion of less than 20 mrad, at any location near groundlevel which could be occupied by individuals at orbeyond the boundary of the site.

d. The annual total quantity of all radioiodines and radio-active material in particulate forms with half-livesgreater than eight days, above background, from allreactors at a site should not result in an annual doseto any organ of an individual in an unrestricted areafrom all pathways of exposure in excess of 15 mrem.

e. The annual total quantity of iodine-131 discharged fromeach reactor at a site should not exceed 1 Ci.

2.4.1. Li uid Waste Effluentsa. The concentration of radioactive materials released in

2-5 Rev. 4 7/28/75

b.

c ~

d.

e.

go

h.

"liquid waste effluents from all reactors at the siteshall not exceed the value specified in 10 CFR Part 20,Appendix B, Table XI, Column 2, for unrestricted areas.The cumulative release of radioactive materials, in liquidwaste effluent excluding tritium and dissolved gases,shall not exceed 10 Ci/reactor/calendar quarter.The cumulative release of radioactive materials inliquid waste effluents, excluding tritium and dissolvedgases, shall not exceed 20 Ci/reactor in any 12 con-secutive months'.During release of radioactive wastes, the effluent con-trol monitor shall be set to alarm and to initiate theautomatic closure of each waste isolation valve priorto exceeding the limits specified in 2.4.l.a above,except as provided in 2.4.2.d below.The operability of each automatic isolation valve inthe liquid radwaste discharge lines shall be demon-strated quarterly.The equipment installed in the liquid radioactive wastesystem shall be maintained and shall be operated toprocess radioactive liquid wastes prior to their dis-charge when the projected cumulative release couldexceed 1.25 Ci/reactor/calendar quarter, excludingtritium and dissolved gases.The maximum radioactivity to be contained in any liquidradwaste tank that can be discharged directly to the

. environs shall not exceed 10 Ci, excluding tritium anddissolved gases.Xf the cumulative release of radioactive materials inliquid effluents, excluding tritium and dissolved gases,exceeds 2.5 Ci/reactor/calandar quarter, the licenseeshall make an investigation to identify the causes forsuch releases, define and initiate a program of actionto reduce such releases to 'the design objective levelslisted in Section 2.4, and report these actions to theNRC in accordance with Specification 5.6.2.b(1) .An unplanned or uncontrolled offsite release of radio=active materials in liquid effluents in excess of 0.5curies requires notification. This notification shallbe in accordance with Specification 5.6.2.b(3) ~

2.4.2 Li uid Waste Sam lin and Monitorin

a ~ Plant records shall be maintained of the radioactiveconcentration and volume before dilution of liquid.waste intended for discharge and the average dilutionflow and length of time over which each dischargeoccurred. Sample analysis results and other reportsshall be submitted as required by Section 5.6.1

of'heseSpecifications. Estimates of the sampling andanalytical errors associated with each reported valueshall be included.

2-6 Rev. 4 7/28/75

b. Prior to release of each batch of liquid waste, asample shall be taken from that batch and analyzed .-

for the concentration of each significant gama energypeak in accordance with Table 2.4-1 to demonstratecompliance with Specification 2.4.1 using the flowrate into which the waste is discharged during theperiod. of discharge.

When operational or other type of limitations pre-clude specific gamma radionuclide analysis of eachbatch, gross radioactivity measurements shall bemade to estimate the quantity and concentrations ofradioactive material released in the batch. A weeklysample, composited from proportional aliquots fromeach batch released during the week, shall be analyzedfor the principal gamma-emitting radionuclides.

co

d.

Sampling and analysis of liquid radioactive waste shallbe performed in accordance with Table 2.4-1. PlantProcedures shall be developed to ensure samples takenfrom liquid batches for release to the environment arerepresentative of the activity actually released.The radioactivity in liquid wastes shall be continuouslymonitored and recorded during release. Whenever thesemonitors are inoperable for a period not to exceed 72hours, two independent samples of each tank to be dis-charged shall be analyzed and two plant personnel shallindependently check valving prior to the discharge. Xfthese monitors are inoperable for a period exceeding72 hours, no release from a liquid waste tank shall bemade and any release in progress shall be terminated.

e. The flow rate of liquid radioactive waste shall be con-

gi

tinuously measured and recorded during release. Xf theflow monitors are inoperable prior to a release, itshall be determined prior to the release, that even atthe maximum design flow rate of the system, applicableactivity release limits will not be exceeded.All liquid effluent radiation monitors shall be calibratedat least quarterly by means of a radioactive sourcewhich has been calibrated to a National Bureau of Stan-dards source. Each monitor shall also have a functionaltest monthly and an instrument check prior to making arelease.The radioactivity in steam generator blowdown shall becontinuously monitored arid. recorded. With one .steamgenerator monitor inoperable, the sampling system shallbe realigned so that the operable monitor is receivingflow from both steam generators. Whenever both monitorsare inoperable, the blowdown flow shall be diverted tothe waste management system and the direct release tothe environment terminated.

2-7 Rev. 4 7/28/75

Bases: The release of radioactive materials in liquidwaste effluents to unrestricted areas shall not exceedthe concentration limits specified in 10 CFR Part 20 andshould be as low as practicable in accordance with therequirements of 10 CFR Part 50.36a. These specificationsprovide reasonable assurance .that the resulting annualdose to the total body or any organ of an individual in anunrestricted area will not exceed 5 mrem. At the sametime, these specifications permit the flexibilityofoperation, compatible with considerations of health andsafety, to assure that the public is provided a depen-dable source of power under unusual operating conditionswhich may temporarily result in releases higher thanthe design objective levels but still within the concen-tration limits specified in 10 CFR Part: 20. It is ex-pected that by using this operational flexibilityunderunusual operating conditions, and exerting every effortto keep levels of radioactive material in liquid wastesas low as practicable, the annual releases will not ex-ceed a small fraction of the concentration limits spe-cified in 10 CFR Part 20.

The design object. ives have been developed based on op-erating experience taking into account a combination ofvariables including defective fuel, primary systemleakage, primary to secondary system leakage, steamgenerator blowdown and the performance of the variouswaste treatment systems, and are consistent with Ap-pendix I to 10 CFR Part 50.

Specification 2.4.l.a requires the licensee to limitthe concentration of radioactive materials in liquidwaste effluents released from the site to levels speci-fied, in 10 CFR Part 20, Appendix B, Table II, Column

2,'orunrestricted areas. This specification providesassurance that no member of the general public will beexposed to liquid containing radioactive materials inexcess of limits considered permissible under the Com-mission's Regulations.

Specifications 2.4.l.b and 2.4.l.c establish the upperlimits for the release of radioactive materials inliquid effluents. The intent of these Specificationsis to permit the licensee the flexibilityof operationto assure that the public is provided a dependable sourceof power'nder unusual operating conditions which maytemporarily result in releases 'higher than the levelsnormally achievable when the plant and the liquid wastetreatment systems are functioning as designed. Releasesof up to these levels will result in concentrations ofradioactive material in liquid waste effluents at smallpercentages of the limits specified in 10 CFR Part. 20.

Consistent with the requirements of 10 CFR Part 50,Appendix A, Design Criterion 64, Specifications 2.4.l.d

2-8 Rey. 4 7/28/75

and 2.4.1.e require operation of suitable equipment tocontrol and monitor the releases of radioactive materialsin liquid wastes during any period that these releasesare taking place.

Specification 2.4.l.f requires that the licensee maintainand operate the equipment installed in the liquid wastesystems to reduce the release of radioactive materials inliquid effluents to as low as practicable consistentwith the requirements of 10 CFR Part 50.36a. Normal useand maintenance of installed equipment in the liquidwaste system provides reasonable assurance that the quan-tity released will not exceed the design objective. Inorder to keep releases of radioactive materials as low aspracticable, the specification requires operation ofequipment whenever it appears that the projected cumula-tive discharge rate will exceed one-fourth of this designobjective annual quantity during any calendar quarter.

Specification 2.4.l.g restricts the amount of radioactivematerial that could be inadvertently released to the en-vironment to an amount that will not exceed the TechnicalSpecification limit.In addition to limiting conditions for operation listedunder Specifications 2.4.1.b and 2.4.1.c, the reporting-requirements of Specification 2.4.l.h delineate that thelicensee shall identify the cause whenever the cumulativerelease of radioactive materials in liquid waste effluentsexceeds one-half the design objective annual quantityduring any calendar quarter and describe the proposedprogram of action to reduce such releases to design ob-jective levels on a timely basis. This report must befiled within 30 days following the calendar quarter inwhich the release occurred as required by Specification5.6.2 of these Technical Specifications.

Specification 2.4.l.i provides for reporting spillage orrelease events which, while below the limits of 10 CFRPart 20, could result in releases higher than the designobjectives.

The sampling and monitoring requirements given underSpecification 2.4.2 provide assurance that radioactivematerials in liquid wastes are properly controlled andmonitored in conformance with the requirements of DesignCriteria 60 and 64. These requirements provide the datafor the licensee and the Commission to evaluate the plant'sperformance relative to radioactive liquid wastes re-leased to the environment. Reports on the radioactive

2-9 Rev. 4 7/28/75

materials released in liquid waste effluents are furnishedto the Commission according to Section 5.6.1 of theseTechnical Specifications. On the basis of such reportsand any additional information the Commission may obtainfrom the licensee or others, the Commission may fromtime to time require the licensee to take such actionas the Commission deems appropriate.

The points of release to the environment to be monitoredin Section 2.4.2 include all the monitored release pointsas provided for in Table 2.4-3.

2.4.3 Gaseous Waste EffluentsThe terms used in these Specifications are as follows:

subscript v, refers to vent releasessubscript i, refers to individual noble gas nuclide

(Refer to Table 2.4-5 for the noble gas nuclidesconsidered)

QT = the total noble gas release rate (Ci/sec)

ZQi sum of the individual noble gas radio-nuclides determined to be present by isotopicanalysis

K = the average total body dose factor due to gammaemission (rem/yr per Ci/sec)

L = the average skin dose factor due to beta emissions(rem/yr per Ci/sec)

M = the average air dose factor due to beta emissions(rad/yr per Ci/sec)

N = the average air dose factor due to gamma emissions(rad/yr per Ci/sec)

The values of K, L, M and N are to be determinedeach time isotopic analysis is required as delineatedin Specification 2.4.4. Determine the followingusing the results of the noble gas radionuclideanalysis:

K = (1/ T) EQj.Ki3.

L = (1/QT) EQiLi3.

M = (1/QT) EQiMi3:

N = (1/QT) EQiNj.3.

where the values of Kj I Lj I Mj and Ni are providedin Table 2.4-5, and are site dependent gamma and

2-10 Rev. 4 7/28/75

dose factors

Q = the measured release rate of the radioiodinesand radioactive materials in particulate formswith half-lives greater than eight days.

a ~

(2)

The release rate limit of noble gases from thesite shall be such that2.0 QTvKv < 1

and

QTv( v + 1.1Nv) 1

The release rate limit of all radioiodines andradioactive materials in particulate form withhalf-lives greater than eight days, releasedto the environs as part of the gaseous wastesfrom the site shall be such that5.5 x 10 Qv

b. (1) The average release rate of noble gases fromthe site during any calendar quarter shall besuch that

QTv vand

(2)

(3)

(4)

6 3 QTv~v

The average release rate of gases from the siteduring any 12 consecutive months shall be

25 QTvNv 1

and

13 QTvMv 1

The average release rate per site of all radio-iodines and radioactive materials in particulateform with half-lives greater than eight, daysduring any calendar quarter shall be such that

13 5.5x10 Qv 1

The average release rate per site of all radio-iodines and radioactive materials in particulateform with half-lives greater than eight daysduring any period of 12 consecutive months shall

2-11 Rev. 4 7/28/75

be such that25 5.5xl0 Qv 1

(5) The amount of iodine-131 released during any cal-endar quarter shall not exceed 2 Ci/reactor.

(6) The amount of iodine-131 released during any periodof 12 consecutive months shall not exceed 4 Ci/reactor.

c. Should any of the conditions of 2.4.3.c(1), (2) or (3)listed below exist, the licensee shall make an investi-gation to identify the causes of the release rates, de-fine and initiate a program of action to reduce the re-lease rates to design objective levels listed in Section2.4 and report these actions to the NRC within 30 daysfrom the end of the quarter during which the releasesoccurred.(1) If the average release rate of noble gases from

the site during any calendar quarter is such that

0 QTvNv 1

or

Tv v(2) If the average release rate per s'ite of all radio-

iodines and radioactive materials in particulateform with half-lives greater than eight days during

.any calendar quarter is such that

50 5.5 103 Q.

(3) If the amount of iodine-131 released during anycalendar quarter is greater than 0.5 Ci/reactor.

d. During the release of gaseous wastes from the gas decaytanks, the gaseous discharge monitor shall be operatingand set to alarm and to initiate the automatic closureof the waste gas discharge valve prior to exceeding thelimits specified in 2.4.3.a above. Whenever thismonitor is inoperable for a period not to exceed 72hours, two independent samples of each gas decay tankto be discharged shall be analyzed and two plant per-sonnel shall independently check valving prior to thedischarge. If this monitor is inoperable for a periodexceeding 72 hours, no release from a gas decay tankshall be made and any release in progress shall beterminated. The operability of each automatic isola-tion valve shall be demonstrated quarterly.

e. The maximum activity to be contained in one waste gasstorage tank shall not exceed 110,000 curies (consi-dered as Xe-133).

2-12 Rev. 4 7/28/75

f. An unplanned or uncontrolled offsite release of radio-active materials in gaseous effluents in excess of 15curies of noble gas or 0.02 curie of radioiodine ingaseous form requires notification. This notificationshall be in accordance with Specification 5.6.2.1(3).

2.4.4 Gaseous Waste Sam lin and Monitorin

a. Plant records shall be maintained and reports of thesampling and analyses results shall be submitted inaccordance with Section 5.6 of these Specifications.Estimates of the sampling and analytical error asso-ciated with each reported value should be included.

b. Gaseous releases to the environment, except; from theturbine building ventilation exhaust and as noted inSpecification 2.4.4.c, shall continuously monitoredfor gross radioactivity and the flow continuouslymeasured and recorded. Whenever these monitors areinoperable, grab 'samples shall be taken and analyzeddaily for gross radioactivity. Xf these monitors areinoperable for more than seven days, these releases shallbe terminated.

c. During the release of gaseous wastes from the primarysystem waste gas holdup system, the gross activity mon-itor, the iodine collection device, and tne particulatecollection device shall be operating.

d. All waste gas effluent monitors shall be calibrated atleast quarterly by means of a known radioactive sourcewhich has been calibrated to a National Bureau of Stan-dards source. Each monitor shall have a functional testat least monthly and instrument check at least daily.

e. Sampling and analysis of radioactive material in gaseouswaste, including particulate forms and radioiodines shallbe performed in accordance, with Table 2.4-2.

N

Bases: The release of radioactive materials in gaseouswaste effluents to unrestricted areas shall not exceed theconcentration limits specified in 10 CFR Part 20 and shouldbe as low as practical in accordance with the requirementsof 10 CFR Part 50.36a. These specifications providereasonable assurance that the resulting annual air dose fromthe site due to gamma radiation will not exceed 10 mrad, andan annual air dose from the site due to beta radiation willnot exceed 20 mrad from noble gases, that no individual inan unrestricted area will receive an annual dose to the totalbody greater than 5 mrem or an annual skin dose greater than15 mrem from fission product noble gases, and that the annualdose to any organ of an individual from radioiodines andradioactive material in particulate form with half-livesgreater than eight days will not exceed 15 mrem per site.

2-13 Rev. 4 7/28/75

At the same time these specifications permit the flexi-bility of operation, compatible with considerations ofhealth and safety, to assure that the public is providedwith a dependable source of power'nder unusual operatingconditions which may temporarily result in releases higherthan the design objective levels but still within the con-centration limits specified in 10 CFR Part 20. Even withthis operational flexibilityunder, unusual operating condi-tions, if the licensee exerts every effort to keep levelsof radioactive material in gaseous waste effluents as lowas practicable, the annual releases will not exceed a smallfraction of the concentration limits specified in 10 CFRPart 20.

The design objectives have been developed based on operatingexperience taking into account a combination of systemvariables including defective fuel, primary system leakage,primary to secondary system leakage, steam generator blow-down and the performance of the various waste treatmentsystems.

Specification 2.4.3.a(1) limits the release rate of noblegases from the site so that the corresponding annual gammaand beta dose rate above background to an individual in anunrestricted area will not exceed 500 mrem to the total bodyor 3000 mrem to the skin in compliance with the limits of10 CFR Part 20.

For Specif ication 2. 4. 3. a (1), gamma and beta dose factors forthe individual noble gas radionuclides have been calculatedfor the plant gaseous release points and are provided inTable 2.4-5. The expressions used to calculate these dosefactors are based on dose models derived in Section 7 ofMeteorolo and Atomic Ener -1968 and model techniquesprovided in Draft Regulatory Guide 1.AA.

Dose calculations have been made to determine the siteboundary locatio'n with the highest anticipated dose ratefrom noble gases using on-site meteorological data and thedose expressions provided in Draft Regulatory Guide 1.AA.The dose expression considers the release point location,building wake effects, and the physical characteristics ofthe radionuclides.

The offsite location with the highest anticipated annualdose from released noble gases is 1600 meters in the Northdirection.The release rate Specifications for a radioiodine and radio-active material in particulate form with half-lives greaterthan eight days are dependent on existing radionuclide path-ways to man. The pathways which were examined for these

2-14 Rev. 4 7/28/75

Specifications are: 1) individual inhalation of airborneradionuclides, 2) deposition of radionuclides onto greenleafy vegetation with subsequent'consumption by man, and3) deposition onto grassy areas where milch animals grazewith consumption of,the milk by man. Methods for estimatingdoses to the thyroid via these pathways are described inDraft Regulatory Guide 1.AA. The offsite location withthe highest anticipated thyroid dose rate from radioiodinesand radioactive material in particulate form with half-lives

. greater than eight days was determined using on-site meteor-ological data and the expressions described in Draft Regu-latory Guide 1.AA. Specification 2.4.3.a(2) limits therelease rate of radioiodines and radioactive material inparticulate form with half-lives greater than eight daysso that the corresponding annual thyroid dose via the mostrestrictive pathway is less than 1500 mrem.

For radioiodines and radioactive material in particulate formwith half-lives greater than eight days, the most restrictivelocation is a residence located 3,000 meters in the WSW di-rection (vent X/Q=5. 5x107 sec/m3) .

Specification 2.4.3.b establishes upper offsite levels forthe releases of noble gases and radioiodines and radioactivematerial in particulate form with half-lives greater thaneight days at twice the design objective annual quantityduring any calendar quarter, or four times the design ob-jective annual quantity during any period of 12 consecutivemonths. In addition to the limiting conditions for operationof Specifications 2.4.3.a and 2.4.3.b, the reporting re-quirements of 2.4.3.c provide that the cause shall be iden-tified whenever .the release of gaseous effluents exceedsone-half the design objective annual quantity during anycalendar quarter and that the proposed program of action toreduce such release rates to the design objectives shall bedescribed.

Specification 2.4.3.d requires that suitable equipment. tomonitor and control the radioactive gaseous releases areoperating during any period these releases are taking place.

Specif ication 2. 4. 3. e limits the maximum quantity of radio-active gas that can be contained in a waste gas storage tank.The calculation of this quantity should assume instantaneousground release, a X/Q based 5 percent. meteorology, theaverage gross energy is 0.19~.Mev per disintegration (consi-dering Xe-133 to be the principal emitter) and exposureoccurring at the minimum site boundary radius using a semi-infinite cloud model. The calculated quantity will limit theoffsite d'ose above background to 0.5. rem or less, consistentwith Commission guidelines.

2-15 Rev. 4 7/28/75

Specification 2.4.3.f provides for reporting release eventswhich, while below the limits of 10 CFR Part 20, could resultin releases higher than the design objectives.

The sampling and monitoring requirements given under Speci-fication 2.4.4 provide assurance that radioactive materialsreleased in gaseous waste effluents are properly controlledand monitored in conformance with the requirements of DesignCriteria 60 and 64. These requirements provide the data forthe, licensee and the Commission to evaluate the plant's per-formance relative to radioactive waste effluents released tothe environment. Reports on the quantities of radioactivematerials released in gaseous effluents are furnished to theCommission on the basis of Section 5.6.1 of these TechnicalSpecifications. On the basis of such reports and any addi-tional information the Commission may obtain from the licenseeor others, the Commission may from time to time require thelicensee to take such action as the Commission deems appro-priate.The points of release to the environment to be monitored inSection 2.4.4 include all the monitored release points asprovided for in Table 2.4-4.

Specification 2.4.4.b excludes monitoring the turbine buildingventilation exhaust since this release is expected to be anegligible release point. Many PWR reactors do not haveturbine building enclosures. 'To be consistent in this re-quirement for all PWR reactors, the monitoring of gaseousreleases from turbine buildings is not required.

2.4.5 Solid Waste Handlin and Dis osal

a. 'easurements shall be made to determine or estimate thetotal curie quantity and principle radionuclide compo-sition of all radioactive solid waste shipped offsite.

b. Reports of the radioactive solid waste shipments, vol-umes, principle radionuclides, and total curie quantity,shall be submitted in accordance with Section 5.6.1.

Bases: The requirements for solid radioactive waste handlingand disposal given under Specification 2.4.5 provide assurancethat solid radioactive materials stored at the plant andshipped offsite are packaged in conformance with 10 CFR Part20, 10 CFR Part 71, and 49 CFR Parts 170-178.

2-16 Rev. 4 7/28y75

TABLE 2.4-1RADIOACTIVE LIQUID SAMPLING AND ANALySIS

LiquidSource

A. Monitor Tank Releases

SamplingFre uenc

Each Batch

Type ofctivity Anal sis

7rincipal Gamma Emitters

DetectableConcentrations

(gCi/ml)—.72

5 x 10'

One batch/Month 6issolved Gases 10

Weekly Composite 3 a-La-140,I-131 10"

.3Monthly Composite

r'oss 6

10

-710-'

B. Steam GeneratorBlowdown4

uarterl Com osite 3 r-90, Sr-89

eekly 5,7,8a-La-140, I-131

6issolved GasesOne Sample/Month 43

Principal Gamma Emitters

.-35 x 10

- -75 x 10

10

10

onthly Composite 5 -3 10

Gross aI

Quarterly Composite Sr-90, Sr-895l

I

10'3

5 x 10

1 The detectability limits for activity analysis are based on the technical feasibilityand on the potential significance in the environment of the quantities released. Forsome nuclides, lower detection limits may be readily achievable, and when nuclides aremeasured below the stored limits, they should also be reported.For certain mixtures of gamma emitters, it may not be possible to measure radionuclidesin concentrations near their sensitivity limits when other nuclides are present in thesample in much greater concentrations. Under these circumstances, it will be moreappropriate to calculate the concentrations of such radionuclides using measured ratios

3with those radionuclides which are routinely identified and measured.A composite sample. is one in which the quantity of liquid sampled is proportional tothe quantity of liquid waste discharged.Required only when activity is detected in the Steam Generators by routine analysisor Steam Generator'lowdown monitor and blow down discharge to the circulating watersystem is in progress.To be representative of the average quantities and concentrations of radioactivematerials in liquid effluents, samples should be collected in proportion to the rate of

~ flow of the effluent stream. Prior to analyses, all samples taken for the compositetshould be throughly mixed in order for the composite sample to be representative of theaverage effluent release.

2-17 Rev. 4 7/28/75

6 5For dissolved noble gases in water, assume a MPC of 4 x 10 pCi/ml of water.When operational or other type of limitations preclude specific gamma spectrumanalysis of each tank, gross activity measurements shall be made to estimate thequantity and concentration of radioactive material released in the batch. A week-ly sample composited from proportional aliquots from each batch released duringthe week shall be analyzed for the principal gamma emitting radionuclides.No sampling required when cold and drained.

2-18 Rev. 4 7/28/75

TABLE 2.4-2RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS

GaseousSource

SamplingFrequency

Type ofActivity Analysis

DetectableConcentrgtion(pCi/ml)

A. Waste Gas Decay Tank:Releases

Each Tank Princi al Gamma EmittersH-3

4210 .

10-6

B. Containment PurgeReleases

Each Purge Princi al Gama EmittersH-3

31010

C. Condenser Air Ejector Monthly5,6 Principal Gamma EmittersH-3

42g310 .

10

D. Environmental ReleasePoints

Monthly(Gas Samples)

Weekly (CharcoalSam le)Monthly (CharcoalSam le)Weekly (Particulates)

Monthly Composite4(Particulates)

Quarterly Composite 4

(Particulates)

Princi al Gamma Emitters

H-3

I-131

I-133,I-135

Principal Gamma Emitters(at least for Ba-La-140;I-131)

Gross a

Sr-90, Sr-89

42i310

10

1-12

10-10

10- 1

1-11

1-11

1 II

The above detectability limits for activity and analysis are based on technical feasi-bility and on the potential significance in the environment of the quantities released.For some nuclides, lower detection limits may be readily achievable, and when nuclides

2are measured below the stated limits, they should also. be reported.For certain mixtures of gamma emit'ters, it may not be possible to measure radionuclidesat. levels near their sensitivity limits when other nuclides are present in the sampleat much higher levels. Under these circumstances, it will be more appropriate to cal-culate the levels of such radionuclides using observed ratios with those radionuclideswhich are measurable.Analyses shall also be performed following each refueling, startup, or similar opera-

4tional occurrence which could alter the mixture of radionuclides.To be representative of the average quantities and concentrations of radioactive, materialsin particulate form released in gaseous effluents, samples should be collected in pro-

5portion to the rate of flow of the effluent stream.Required only when activity is detected in the Steam Generator by routine analysis orby the secondary side process monitors.No sampling required if unit is shutdown during the sampling intexval.

2-19 Rev. 4 7/28/75

TABLE 2.4-3ST. LUCIE PLANT LIQUID WASTE SYSTEM

LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS

PROCESS STREAM ORRELEASE POINT

RADIATIONALARM

AUTO CONTROLTO ISOLATIONVALVE

GRAB

CONTINUOUS SAMPLE GROSS

MONITOR STATION ACTIVITYDISSOLVED

GASSESALPHA H-3

MEASUREMENT

ISOTOPICANALYSIS

HIGH LIQ-.UID LEVELALARM

EQUIPMENT DRAINTANKS

CHEMICAL DRAINTANKS

LAUNDRY:'RAINTANKS

LIQUID RADWASTE

DISCHARGE PIPE

S/G BLOWDOWN

SYSTEM X

OUTDOOR STORAGETANKS(POTENTIALLY =-

RADIOACTIVE)

COMPONENT COOLINGSYSTEM X

TABLE 2.4-4ST. LUCIE"PLANT . GASEOUS WASTE SYSTEM

LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS

PROCESS STREAM OR

RELEASE POINT

AUTO CONTROLTO ISOLATIONVALVE

CONTINUOUSMONITOR

GRABSAMPLESTATION NOBLE

MEASUREMENT

GAS I PARTICULATE H-3

GAS DECAY TANK EFFLUENT X - X X X

CONDENSER AIR EJECTOR

BUILDING VENTILATEDSYSTEMS

X X X

PLANT VENT

FUEL HANDLING ANDSTORAGE BUILDING

X X

X X

TABLE 2.4-5

GAMMA AND BETA DOSE FACTORS FOR

ST LUCIE PLANTg UNIT 1

-6 3X/Q = 2,1 x 10 sec/m

DOSE FACTORS FOR VENT.

NOBLE GASRADIONUCLIDE

K.avTotal Bodyrem/yrCi/sec

L.iVSkinrem/yrCi/sec

MiVBeta Air

rad/yr'i/sec

N.iVGamma Air~rad/ r

Ci/sec

S

Kr-83m

Kr-85m

Kr-85

Kr-87

Kr-88

Kr-89

Xe-131m

Xe-133m

Xe-133

Xe-135m

Xe-135

Xe-137

5.8 x 10

0.88

0. 014

1.9

6.0

0,5

0.4

0.3

0. 36

0.64

1.5

0. 072

0

3.1

2.8

20

5.0

21

1.0

2.1

0. 64

1.5

3.926

0.6

4.1

4,122

6.2

22

2.3

3.12.2

1.65.2

27

0. 028

0. 92

0. 015

2.0

6.3

0.52

0.5

0. 41

0. 45

0.68

1.60. 076

(c) If the amount of iodine-131 released during any calendarQuarter is greater than 0.5 Ci/reactor.

PWR Unplanned or Uncontrolled Release Report. Any unplanned oruncontrolled offsite release of radioactive materials in excessof 0.5 Curie in liquid or in excess of 15 Curies of noble gasesor 0.02 Curie of radioiodines in gaseous form requires notifi-cation. This notification must be made by a written reportwithin 30 days to the NRC. The report shall describe the event,identify the causes of the unplanned or uncontrolled release andreport actions taken to prevent recurrence.

2-23 Rev. 4 7/28/75

3.0 ENVIRONMENTAL SURVEILLANCE

3.1 Non-radiolo ical Surveillance

3.1.A ABIOTIC

3.1,A.1 Biocides

The purpose of this surveillance is to monitor TotalResidual Chlorine in the discharg canal to insurethat no adverse impact on the environment is occurring.

S ecification

Total Residual Chlorine shall be mcnitored in thedischarge canal on a weekly basis while a condenser.section is being chlorinated. See Section 2.2.1for limiting conditions.

t

Re ortin Re uirement

,Total Residual Chlorine 'concentration shall bereported in the Annual Environmental OperatingReport.

Ob 'ective

The purpose of this study is;to monitor heavy metalsconcentrations in the intake and discharge canalsto detect any measurable increase in heavy metals.

S ecificationGrab samples shall be taken on a monthly'asis atthe intake and discharge canals and analyzed forMercury, Arsenic, Chromium, Copper, Iron, Lead,Nickel, and Zinc.

Re ortin Requirement

Concentrations shall be reported in the AnnualEnvironmental Operating Report.

3-1 Rev. 4 7/28/75

f) Mi rator Sea Turtles — The species, numbers,and nesting characteristics of sea turtles thatmigrate in from the sea and nest. along the eastcoast of Florida will be determined on the FPLshoreline property, and selected adjacent controlareas in 1975 and 1977. A study shall be conductedto determine the effects of the discharge thermalplume on turtle nesting patterns and turtle

'atchli:ngmigration. In addition, control studieson temperature stress,'atching, and rearing factorswill be conducted using turtle eggs from displacednests.

Based on the data obtain=d, predictions will be madeon the impact of the plant's operation on baselinebiological conditions and current uses of the waters.

Florida Power & Light will review the data after twoyears of plant operation. ,If effects attributableto the plant are found acceptable, the results shallbe reviewed by NRC to determine if the biotic program,or any portion thereof, should be terminated.

Re ortin Re uirement

Results of the biological program shall be reportedin the Annual Environmental Operating Report.

'3-5 Rev. 4 7/28/75

3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING

The Operational Radiological Environmental SurveillanceProgram is conducted to measure radiation levels andradioactivity in the environs, and to assist in verify-ing any projected or anticipated radioactivity releaseresulting from plant operations which could bring aboutpublic exposure to radiation.S ecifications3.2.a Environmental samples shall be collected at the

designated locations shown in TABLE 3.2-.1 andFIGURES 3.2-.1 and 3.2-.2.

3,2,b The criteria for the type and the number of samplesto be collected at a given sampling location, thefrequency of collection, and the type and frequencyof radioactivity analysis to be completed on thecollected samples shall be as shown in TABLE 3,2-2.

Direct,radiation shall be measured by thermolumine-scence dosimetry (TLD) at locations. shown in TABLE3.2-1 and FIGURES 3.2-1 and 3.2-2. The system shallbe capable of measuring 25.8 mrad/year at the 90%confidence level based on a quarterly collectionfrequency.

3,2.c The radiation detection capabilities of the radio-analytical methods used shall be as shown in TABLE3 ~ 2 3 ~

3.2.d A census of gardens producing fresh leafy vegetationfor human consumption shall be conducted near theend of the growing season to determine their locationwith respect to the plant site. This census islimited to gardens having an area of 500 ft2 or more/and shall be conducted under the following conditions:

1) Within a 1 mile radius of the plant site,enumerated by door-to-door or equivalentcounting technique.

2) If no milk-producing animals are locatedin the vicinity of the site, as determinedby Specification (e) below, the censusdescribed in item (1) above,'hall beextended to a distance of 5 miles fromthe site.

3) If this census reveals the existence of agarden at a location yielding a calculatedthyroid dose greater than that from apreviously sampled garden, the new locationshall replace the garden previously havingthe maximum iodine concentration. Also,any location from which fresh leafy vegetables

3-6 Rev. 4 7/2 8/75

can no longer be obtained may be droppedfrom the surveillance program after notifyingNRC in writing that such vegetables are nolonger grown at that location.

3.2. e A census of animals producing milk for humanconsumption shall be conducted semiannuallyto determine their location and number withrespect to the plant site. The census shallbe conducted under the following conditions:

1) Within a 1 mile radius from the plant site orwithin a 15 mrem/year isodose line (ascalculated using dose models presented inRegulatory Guide 1. 42), whichever is larger,enumeration by a door-to door or equivalentcounting technique.

2) Within a 5 mile radius for cows and a 15 mileradius for goats, enumeration by using refer-enced information from county agriculturalagents on other reliable sources.

3.2. f

If it is determined from the census that animalsare present at a location which'ields a calculatedthyroid dose greater than that from previouslysampled animals, the new location shall be addedto the surveillance program as soon as practicable.The sampling location having the lowest calculateddose may be dropped from the surveillance program3 months after sampling begins at the new location.,Also, any location from which milk can no longer beobtained may be dropped from the surveillance programafter notifying NRC in writing that milk-producinganimals are no longer present at that location.Deviations from the required sampling schedule arepermitted if specimens are not obtainable due tohazardous conditions, seasonal unavailability, or.malfunction of automatic sampling equipment. Inthe latter case, every reasonable effort shall bemade to complete corrective action prior to theend of the next sampling period. All deviationsfrom the'ampling schedule shall be described inthe annual report.A deviation of not greater than one week from therequired frequency of analysis for grass betaactivity, as shown in TABLE 3.2-2, is permitted ifequipment failure delays the analyses, Everyreasonable effort shall be made to effectexpeditions equipment repair.

Re ortinAll required reports from this Operational RadiologicalEnvironmental Surveillance Program shall be prepared andpresented in the manner described in Section 5.6.1.B ofthese Environmental Technical Specifications.

3-7 Rev, 4 7/28/75

Bases

The program is designed to determine existing radio-activity levels and to detect changes in radiation levelsin the air, water and land environment which may beattributed to the operation of the plant. The methods,procedures and techniques used were developed duringthe preoperational phase and have provided backgroundmeasurements that will be used as a base for distinguishingsignificant changes in radioactivity in the site environs.

3-8 Rev. 4 7/28/75

TABLE 3. 2-1

ST. LUCIE PLANT

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM

SAMPLING LOCATIONS AND VECTORS SAMPLED

StationNo. Descri tion B~earin * Distance* Vector Sam ledH03 Meadowbrook Dairy, Glades Cut-off Ro'ad, 260 22. 526 km Milk

St. Lucie County (14. 00 mi)

H08 Florida Power & Light Company Substa-tion White City, Weatherby Road westof U. S. 1

293 9. 170 km Soil, Air Particulates & Iodine,(5.7 mi) . Direct Radiation

H09 Florida Power & L'ight Company Substa-tion west of U.S. 1, just south ofSt. Lucie County Line

196 11.745 km Soil, Air Particulates & Iodine,(7.30 mi) Direct Radiation

H10 Indian. River Field Laboratory, Univer-sity of Florida, west of SR 713

300 19.308 km Food Crops (Citrus), Air Particulatesh(12.00 mi) Iodine, Direction Radiation, Soil

Hll City of Ft. Pierce, Water System—Collected at St. Lucie County HealthDepartment, Ave., *"C", Ft. P'ierce

323 14.480 km Potable Water (Well) — City of Ft.(9 mi) Pier'ce

H12 Florida Power & Light Company Substa-tion SR 76 west of U.S. 1, Stuart,Martin County

180 19.308 km Potable Water (Well) — City of Stuart,(12.00 mi) Air Particulates & Iodine, Direct

Radiation

~ H13 On Site, Point north of Big Mud Creekat Indian River

312 1021 m Surface Water, Bottom Sediment(0. 63 mi) (Estaurine)

StationNo.

Descri tion

TABLE 3.2-1 (Continued)

B~earin * Distances Vector Sam led

H14 Employees Parking Lot, southeast ofContainment

160 503 m Air Particulates & Iodine, Direct(0.31 mi) Radiation

H15 On Site, Beach near Discharge Structure 89 808 m Ocean Water & Bottom Sediment,0

(0,.50 mi) Aquatic Biota

H16 Beach (ocean) opposite Blind Creek 31 1509 m(0.94 mi)

Ocean — Bottom Sediment, Beach Sand

H19 On Site, Beach south of Intake Canal 161 1494 m(0. 90 'mi)

Ocean — Bottom Sediment, Beach Sand

H22 Lentz Groves, U.S. 1 210 8.849 km 'ood Crop (Citrus)(5.50 mi)

H23 Montauk Groves, U.S. 1, south ofEasy Street

270 7.562 km Food Crop (Citrus),(4. 70 mi)

H24 Poster Groves, U.S. 1, north ofTumblin Kling Road

300 8.608 km Food Crop (Citrus)(5. 35 mi)

H25 Childs Groves, Bell Avenue, west ofSunrise Blvd.

297 11. 263 km Food Crop (Citrus)(7. 00 mi)

I~H26 Wouters Groves, west of SR 713 on

Immokola Road.314 21.720 km Food Crop (Citrus)

(13.50 mi)

H30

~]

Residence, 7609 Indian River Drive 245 3. 218 km(2.00 mi)

Ground Water (Well), Soil, AirParticulates & Iodine, DirectRadiation

'I

StationNo. Descri tion

TABLE 3, 2-1 (Continued)

Bearing* Distance* Vector Sam led

H31 North Port St. Lucie Water System,Prima Vista Blvd.

250 10.619 km(6.60 mi)

Potable Water (Well) — Port.St. Lucie

H32 Department of Health and Rehabilit-ative Services Entomology Laboratory,East of U.S. 1, Vero Beach

338o 30.571 km(19.00 mi)

Aquatic Biota, Ocean Water 6Bottom Sediment, Air Particulates6 Iodine, '.Soil, Direct Radiation,Beach Sand

H33 On Site, between Canals, east of AIA 138o 945 m(0. 59 mi)

Air Particulates 5 Iodine, DirectRadiation

H34 On Site, Meteorological Tower 27 762 m(0.47 mi)

Air Particulates 6 Iodine, DirectRadiation

lH36 On Site, Discharge Canal west of AIA 101 305 m . Surface Water, Bottom Sediment

(0,19 mi)

H39 Vista Royal Condominium, 1 mile northof H32, east of U.S. 1, Vero Beach

338o 32.180 km(20,00 mi)

Food Crop (Citrus)

H40 Florida Milk Shed Milk

*Bearings and distances from the center of Generating Stations.

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ISO C

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. Il SVQ~~IIIIIIIev' (

~ sea P» LCCCIIOovvotsvoe ol aao w Je

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~ AIR PARTICULATEAIR IODINESTLD LOCATIONS

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RADIOLOGICALENVIRONMENTALSURVEILLANCEST. LUCIE PLANT

, SAMPLING LOCATIONS I~

«fj ea

OT. LII

I~ 4» -'=-IH'o9a ~

JQC('

ST. LUCIE Co~tTYFLORIDA

~il~ ia ~ ioi

Jaa!Es W. Basssi- \ ~

e el C

FIGURE 3.2-l

e al I I saLI 0 Ia

tl

II Oea C

Pa

Nve I~

WN Oli ~ ~~ vl INC

~ «444 OJONC oaa ovev

'IN le Aver ~ IIlac IONIIooel oeCOCC,OLOIIIOO

P aL Rev. 4 7/28/75

ST. LUCIE PLANT

SAMPLING LOCATIONSFIGURE 3.'2-2

~ (INSET TO FIGURE 3.2-1)

B.hhl7'RoeeRv v Lwz5'.ISO.'.FliOÃ,.,li'EACYOR Sll.E

BLIPS'4 CWEEK

H34

S&de Rc w4AgA

Sn.idge

disc4qge(Ahlh(

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HI4 H'H

t

0

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PLAMr. PRopzpr..y l.iek .'loo

. F,ITO!d RBjtC7oR SI7.8

3-13 ReV, 4 7/28/75.

TABLE 3, SHEET 1

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM

ST. LUCIE PLANT

Exposure Pathwayand/or Sam le

1. AIRCriteria and Sam lin Locations

CollectionFre uenc

Type and Frequencyof Anal sis

1.1 Particulate andIodine

1.2 Direct Radiation

2. WATER

Comparison on-site versus off-site6 reference locations:3 locations on-site, north, east,a southeast of the plant: H 34,H14, H 335 locations off-site within aradius of 10 miles of plant~H 08,H 09, H 10, H 12, H 30, and 1 controllocation: H32Comparison of on-site versus off-site 6 reference locations:3 locations on-site, north, east,6 southeast of the plant: H 34,H14, H335 locations off-site within aradius of 10 miles of plant: H 08,H 09, H 10, H 12, H 30, and 1 controllocation: H32

Weekly

Quarterly

~ \

Gross BetaGamma spectral analysis

of monthly compositeRadioactive IodineSr-89 6 90 (Quarterly Composite)

Determine direct radiationby exposure by TLD readout(mean of 2 TLDs)

2.1 Surface Water

2.1.1 Discharge Canal 1 location,. west of AIAg H36 Monthly Gamma spectral analysisTritium (Quarterly Composite)Sr-89 s 90 (Quarterly Composite)

2.1.2 Ocean

2.1.3 Estuarine

2 locations; H15 6 H32 (Control)

1 location; Big Mud Creek: H13

Monthly

Quarterly

Gamma spectral analysisTritium (Quarterly Composite)Sr-89 6 90 (Quarterly Composite)

Gamma spectral analysisTritium

2.2 Ground Water (well) 1 location~ Residence, 7609 IndianRiver Drive: H30

,Semi-annually Gamma Spectral AnalysisGross BetaTritium

TABLE 3. SHEET 2

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM

ST. LUCIE PLANT

Exposure Pathwayand/or Sam le Criteria and Sam lin Locations

CollectionFre uenc

Type and Frequencyof Analysis

2. WATER (cont'd)

2.3 Potable Water(wells)

1 location, City of Ft. Pierce,drinking water supply, H ll1 location~ City of Stuart,drinking water supply, H 121 location, Port St. Lucie,drinking water supply, H 31 .

Quarterly Gamma spectral analysisGross BetaTritium

3. BOTTOM SEDIMENT

3.1 Discharge Canal 1 location< west of AIA: H36 Semi-annually Gamma spectral analysisSr-90

3. 2 Ocean 1 location, beach west of dischargestructure: H151 location, offshore, 1 mile northof discharges: H161 location, offshore, 1 mile southof discharge: H191 location, offshore, Vero Beach:H32 -(Control)

Semi-annually Gamma spectral analysisSr-90

3.3 Beach (sand) 1 location, east of Blind Creek, 1mile north of discharge: H161 location, near intake, 1 milesouth of discharge: H191 location, Vero Beach: H32 (Control)

Semi-annually Gamma spectral analysisSr-90

3.4 Estuarine 1 location, Big Mud Creek: H13 Semi-annually Gamma spectral analysis

4.1 Crustacea(Lobster or crabor shrimp)

1 location, vicinity of dischargestructure: H15

~ . 1 location, Vero Beach: H32 (Control)

Semi-annually Gamma spectral analysis

TABLE 3. SHEET 3

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM

ST. LUCIE PLANT

Exposure Pathwayand/or Sam le Criteria and Sam lin Locations

CollectionFre uenc

Type and Frequencyof Analysis

4. AQUATIC BIOTA(cont'd)

4.2 Fish

4.2.1 Carnivores ,1 location, vicinity of dischargestructure: H 151 location, Vero Beach: H32 (Control)

Semi-annually Gamma spectral analysisSr-89 6 90

4.2.2 Herbivores 1 location, vicinity of dischargestructure: H151 location, Vero Beach: H32 (Control)

Semi-annually Gamma spectral analysisSr-89 6 90

5., TERRESTRIALs.

1 location within 15 mile radius Semi-monthlyof plant and in the prevailingwind direction from the plant: H03

Gamma spectral analysisSr-89 6 901-131

1 location, Florida (state) MilkShed: H)0 (Control)

Monthly Gamma spectral analyyisSr-89 6 90I-131

Dairy herd census Semi-annually

5.2 Biota

5.2,1 Food Crop(Citrus)

5.2.2 Pood Crop(Edible Leafyvegetation)

6 locationsg H10g H22g H23p H24IH25i H26

1 location as determined by gardencensus (Specification 3,2,d)

Harvest Time

Harvest Time

Gamma spectral analysisSr-89 a 90

Gamma spectral analysiaI-131

5.3 Soil 5 locations within a 15 mile radius Once per 3-yearof plant: H03, H08, H09, H10, H30. period1 location, Vero Beach: H32 (Control)

Gamma spectral analysisSr-90

TABLE 3.2-3

St. Lucie Plant: Detection Ca abilities for Environmental Sam le Anal sisMedia Dete"tion Capabilities*

Analysis

Gross beta3H

. '4Mn

59 Fe

58Co

60

65I Zn

89 Sr90SSr95 Zr-Nb

3.31

134CCs

137CCs

140 Ba-La

Water(pCi/1)

0.8199.0

6.0

7.0

7.0

14. 0

1.6

0.8

7.0

7.6

6.0

7.0

8.0

Airborne Particulatesor Gas

( Ci/m3)

0. 002.

0.005

0.002

0.008

0.008

0.008

0.008

F1sh i Meator Poultry(PCi/k ,wet)

17.0

5.0

19.0

20.0

39.0

8.0

4.0

18. 0

18. 0

Milk(pCi/1)

2.0

1.0

0-5

6.0

7.0

Vegetation(pCi/kg,wet)

16.0

Soil(pCi/kg,dry)

10.0

26.0

26.0

o< *Nominal: LLD's (lower limit of detection) calculated as defined in HASL-300, Rev. 8/73, pp 08-01,~ 02, 03, at the 90% confidence level. The detection levels for radionuclides analyzed by gammaspectrometry- will vary according to the number of radionuclides encountered in environmental samples.

Vl

3'.3 ONSITE METEOROLOGICAL MONITORING

Ob'ective

The objective of onsite meteorological monitoring is toadequately measure and document meteorological conditionsat the site, specifically at heights above ground thatare represe'ntative of atmospheric conditions that existat all effluent release points.

S ecificationThe onsite meteorological monitoring program shall conformto the recommendations and intent of Regulatory, Guide 1.23,Onsite Meteorolo ical Pr'o rams, and include instruments tosense wind speed and dz.rection at 33-ft and 190-ft, verticaltemperature gradient between 33-ft and 200-ft, and ambientdry bulb and dewpoint temperatures at, 33-ft. he locationof the meteorological tower shall be located approximately2400 feet north of the reactor complex.

Re ortin Requirements

Meteorological data shall be summar'"ed and reported in aformat consistent with the recommendations of Regulatory .

Guides 1.21 and 1.23. Summaries of data andobservations shall be available to the U. S. NuclearRegulatory Commission upon request. If the outage of anymeteorological instrument(s) exceeds three consecutivedays,. the total outage time and dates of outage, the causeof the outage, and the instrument(s) involved sha'1 bereported within 30 days of the initial time of the outageto the U. S. Nuclear Regulatory Commission, Office ofInspection and Enforcement with a copy to the

Office'of'uclear

Reactor Regulation, Division of Techni'cal Review.Any modifications to, the meteorological monitoring programas described above, or alterations of the area near themeteorological tower that would interfere w'ith the measure-ment of meteorological conditions representative of thesite, shall have the written approval of the U. S. NuclearRegulatory Commission, Office of Nuclear Reactor Regulation,prior to the initiation of the modification or alteration.Bases

'The collection of meteorological data at the plant site willprovide information which will be used to develop atmosphericdiffusion parameters to estimate potential radiatio'n doses tothe public resulting from actual routine or accidental releasesof radioactive materials to the atmosphere.

:3-18 Rev. 4 7/28/75

4.0 SPECIAL SURVEILLANCE AND SPECIAL STUDY ACTIVITIES

Entrainment of Aquatic Or anisms

The purpose of this study is to assess the effects onplanktonic organisms of passage through the plantcondensers. Specialists in the biological sub-disciplinesof zooplankton. and ichthyology will perform appropriateportions of this study. Figures obtained for the intakeand discharge canals will be compared to data collected ata control station.

~S ecificationSamples shall be collected from the intake and dischargecanals and a control station at monthly intervals whenthe unit is in operation to identify the organisms involved,and to attempt to quantify how many of each organism arepotentially affected. Biomass measurements, numbers ofeggs collected, and numbers and identification of larvae-to the level of major taxonomic groups, if possible — shallbe performed. Present "state-of-the-art" information shallbe used to attempt to quantify the mortality of the organismsdue to entrainment. This program shall determine theseasonal abundance of fish eggs and larvae.Re ortin Re uirements

4.2

Results. of this study shall be summarized in the AnnualEnvironmental Report, If, at the end of two years, nosignificant problem is evident, an option to formally deletethis portion of the Tech Specs may be initiated.Im in ement of A uatic Organisms

Ob'ective

The purpose of this study is to assess the impingementof aquatic organisms on intake screens and the environmentalimpact of the impingement.

S ecificationIntake screens washings shall be examined for aconsecutive twenty-four hour period, twice a weekwhenever the Unit 1 circulating water pumps areoperating. The collected washings shall be analyzed.for the species present, number of each individualspecies caught, total biomass of each species, andthe average size of the individuals caught.Re ortin Regula,rements

Data collected shall'be analyzed monthly for the firstyear of operation and a report sent to the NRC within45 days of each monthly period. After the first yearof operation, the data shall be analyzed every sixmonths, and the results summarized in the AnnualEnvironmental Report.

4-1 Rev. 4 7/28/75

4.3 Minimum Effective Chlorine Usa e

Ob'ective

The purpose of this study is to determine the minimumamount of chlorine necessary which will afford adequateprotection to the condenser while avoiding unnecessaxydischarge of chlorine to the environment.

S ecificationA program shall be initiated after Unit 1 has initiallyreached 75% power level. The initial chlorine injectionrate shall be determined based on preoperational data,previous experience, and laboratory chlorine demand tests.After reaching a power plateau above 75% power, a controlledincremental reduction of the chlorine injection rate- shallbe implemented, Condenser fouling shall be monitored incoordination with chlorine reduction.

Re ortin Re uirements

The results of this study Shall be summarized in theAnnual Environmental Report. When the minimum levelof chlorine usage, as determined by the study, hasbeen reached, a proposal shall be submitted to theNRC to terminate the study,

4-2 Rev. 4 7/28/75

5.4.4 Each instance whereby a Limiting Conditionis exceeded shall be reported to the CompanyNuclear Review Board.

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

5.5 Procedures

5.5.1 Detailed written procedures, including appli-cable check lists and instructions, shall beprepared and followed for activities involvedin carrying out the environmental technicalspecifications. Procedures shall includesampling, data recording and storage, instru-ment calibration, measurements and analyses,and actions to be taken when limits areexceeded. Testing frequency of any alarmsshall be included.

5.5.2 Plant operating procedures shall includeprovisions to ensure that plant systems andcomponents are operated in compliance withthe environmental technical specifications.

5.6 Re ortin Requirements

5. 6. 1 Routine Re orts5.6.1.A. Annual Non-Radiolo ical Environmental

0 erato.n Re ort

A'eport on the environmental surveillanceprograms for the previous 12 months ofoperation shall be submitted to the Direc-tor of the Regional Office of Inspectionand Enforcement with a copy to „the Direc-tor of the Office of Inspection and En-forcement as a separate document within 90days after January 1 of each year. Theperiod of the first report shall begin withthe -date of initial criticality. The reportshall include summaries and interpretations ofthe results of the non-radiological environ-mental surveillance activities (Section 3.0)and the environmental monitoring programsrequired by Limiting Conditions for. Operation.This should also include a comparison withpreoperational studies, operational controls(as appropriate), and previous environmentalsurveillance reports, and an assessment of theobserved impacts of the plant operation onthe environment, If harmful effects orevidence or irreversible damage are detectedby the monitoring, the licensee shall providean. analysis of the problem and a proposedcourse of action to alleviate the problem.

5-5 Rev. 4 7/28/75

5.6.1.B. Annual'adi'o'lo i'cal Envi'ronmental0 eratzn . Re ortA report on the radiological environ-mental surveillance programs for theprevious 12 months of operation shallbe submitted to the Director of theNRC Regional Office (with a copy tothe Director, Office of Nuclear ReactorRegulation) as a separate documentwithin 90 days after January 1 ofeach year. The period of the firstreport shall begin with the date ofinitial criticality. The reports shallinclude summaries, interpretations, andstatistical evaluation of the resultsof the radiological environmental sur-veillance activities for the reportperiod, including a comparison withpreoperational studies, operationalcontrols (as appropriate), and previousenvironmental surveillance reports andan assessment of the observed impactsof the plant operation on the environ-ment. The reports shall also includethe results of land use censuses requiredby the specif icat ions. If harmfuleffects or evidence of irreversibledamage are detected by the monitoring,the licensee shall provide an analysisof the problem and a proposed courseof action to alleviate the problem.

Results of all radiological environmentalsamples taken shall be summarized on anannual basis. In the event that someresults are not available within the90-day period, the report shall be sub-mitted noting and explaining the reasonsfor the missing results. The missingdata shall be submitted as soon aspossible in a supplementary report. ~

5.6.1.C Annual Radioactive Effluent Release Re ortA report on the radioactive dischargesreleased from the site during the previous12 months of operation. shall include thefollowing:Analyses of Effluent releases shall be sum-mariz'ed on a quarterly basis and reportedin a format similar to Tables 5.6.1-A,B,C,GD.Supplemental information shall be includedcovering topics similar to those itemizedin Data Sheet 5.6.1-1.

5-6 Rev.4 7/28/75

Abnormal releases should be handled asbatch releases for accounting purposes.-

Solid wastes shall be summarized on aquarterly basis and reported in a for-mat similar to that of Table 5. 6. 2-E.

The following information should bereported for shipments of solid wa teand irradiated fuel transported fromthe site during the report period:

1. The annual total quantity in cubicmeters and the annual total radioactivityin curies for the categories or types ofwaste.

a ~

b.

c ~

d.

Spent resins, filter sludges,evaporator bottoms;Dry compressible waste, con-taminated equipment, etc.;Irradiated components, controlrods, etc.;Other (furnish description).

2. An estimate of the total activityin the categories of waste in1) above.

3. The disposition of solid wasteshipments. (Identify the number ofshipments, the mode of transport,and the destination).

4. The disposition of irradiated fuelshipments. (Identify the number ofshipments, the mode of transport,and the destination).

5-6a

Hev. 4 7/28/75

TABLE 5. 6 ~ 1-A

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES

Unit

A. Fission & activation gases

1. Total release

2. Average release rate for period

3. Percent of Technical specification limitpCi/sec

E

E

E

E

E

E

B. Zodines

1. Total iodine-131

2. Average release rate for period

3. Percent of Technical specification limit

Ci

:pCi/sec

E

E

E

E

E

E

C. Particulates

l. Particulates with half-lives 8 days

2. Average release rate for period

3. Percent of Technical specification limit4. Gross alpha radioactivity

pC1/sec

E

E

E

E

E

E

E

E

D. Tritium

1. 'Ibtal release

2. Average release rate for period pCi/sec

E

E

E

5-9 Rev.4 7/28/75.

TABLE 5.6.2-.C

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES

Unit Qu-~r

A. Fissions''and".activation productsl. Total release (not including tr~Mun,

s, al ha)2. Average diluted concentration

during period

3. Percent of applicable limit

yCi/ml

E

E

E

E

E

E

B. Tritium

1. Total release2. Average diluted

concentration

dural iod

Ci

pCz/ml

E

E

E

E

1. Total release Ci . E E

2. Average Chluted concentrationdurin riod

3. Percent of applicable limit

D. Gross alpha radioactivity

pCi/ml E

E

E

E

l. Total release E . E

E E

F . Volune of dilution water used during period liters E E

Rev. 4 7/28/75

5-11

5~6<2.. Non Routine Re orts

5.6.2.a No'n',.Ra'di'pact'ice''Effl'uen't: Re orts,A report shall be submitted in the 'eventthat: (a) a limiting condition is ex-ceeded (as specified in Section 2.0Limiting Conditions), or an unusual orimportant event occurs that causes asignificant environmental impact, thataffects potential environmental impactfrom plant operation, or that has highpublic or potential public interest con-cerning environmental impact from plantoperation. Reports shall be submittedunder one of the report schedules des-cribed below.

(1) Prompt Reports

Those events requiring prompt reportsshall be reported within 24 hours bytelephone, telegraph, or facsimiletransmission to the Director of theRegional Office of Inspection andEnforcement and within 10 days by awritten report to the Director of theOffice of Inspection and Enforcement.

(2) 30-Day Reports

Those events not requiring promptreports shall be reported within 30days by a written report to theDirector of the Regional Office ofInspection and Enforcement with a copyto the Director of the Office of In-spection and Enforcement.

The reporting schedule for reports concerninglimiting conditions shall be reported on the30-Day schedule. Reports concerning unusualor important events shall be reported on theprompt schedule.

Written 10-day and 30-day reports and to theextent possible the preliminary telephone,telegr'aph, or facsimile reports shall:(a) describe, analyze, and evaluate theoccurrence, including extent and magnitudeof the impact, (b) describe the cause ofthe occurrence and (c). indicate the correc-tive action (including any significantchanges made in procedures) taken to preclude

5-14Rev. 4 7/28/75

repetition of the occurrence and to preventsimilar occurrences involving similar com-

,ponents or systems.

The significance of an unusual or- apparently .

important event with regard to environmentalimpact may not be obvious or fully appre-ciated at the time of occurrence. In suchcases, the NRC shall be informed promptlyof changes in the assessment of the signifi-cance of the event and a corrected reportshall be submitted as expeditiously aspossible,

5.6;,2.b Radioactive Effluent Re ortsLi uid Radioactive Wastes Re ortIf the cummulative releases of radioactivematerials in liquid effluents, excludingtritium and dissolved gases, should exceedone-half the design objective annual quantityduring any calender quarter, the licenseeshall make an investigation to identify thecauses of such releases and define and initiatea program of action to reduce such releases tothe design objective levels. A written report,of these actions shall be submitted to the NRCwithin 30 days from the end of the quarterduring which the release occurred.

Gaseous Radioactive Wastes Re ortShould the conditions (a), (b), or (c) listedbelow exist, the licensee shall make an invest-igation to identify the causes of the releaserates and define and initiate.a program ofaction to reduce the release rates to designobjective levels. A written report of theseactions shall be submitted to the NRC within30 days from the end of the quarter duringwhich the releases occurred.

(a) If the average release rate of noblegases for the site during any calendarquarter exceeds one-half the designobjective annual quanity.

(b) If the average release rate per site ofall radioiodines and radioactive materialsin particulate form with half-lives greaterthan eight days during any calendar quarterexceeds one-half the design objective annualquantity.

5-15 Rev. 4 7/28/75

(c) If the amount of iodine-131 releasedduring any calendar quarter is greaterthan 0.5 Ci/reactor.

Un lanned or Uncontrolled Release Re ortAny unplanned or uncontrolled offsite releaseof radioactive materials in excess of 0,5 Curiein liquid or in excess of 5 Curies of noblegases or 0,02 Curie of radioiodines in gaseousform requires notification. This notificationmust be made by a written report within 30 daysto the NRC. The report shall describe theevent, identify the causes of the unplanned oruncontrolled release and report actions takento prevent recurrence.

5.6. 2, c 'a'd'io'lo'i'ca'1'nvi'r'onment'a'1 S'u'rv'e'i'll'a'nc'e Re~'o 'ts

If a confirmed measured level of radioactivityin an environmental medium exceeds ten timesthe control station value, a written reportshall be submitted to the Director of the NRCRegional Office (with a copy to the Director,Office of Nuclear Reactor Regulation) within10 days after confirmation of the validity ofthe measured level. Confirmation shall becompleted at the earliest time consistent with wi'7g„the analysis, but in any case,< 30 days. Thisreport shall include an evaluation of anyrelease conditions, environmental factors, orother aspects necessary to explain the anomalousresult.

5.6.3. Chan es in Environmental Technical S ecifications

5.7

Request for changes in environmentaltechnical specifications shall be sub-mitted to the Director of Nuclear ReactorRegulation for review and authorization.The request shall include an evaluationof the environmental impact of the proposedchange.

Records Rentention

5.7.1 Records and logs relative to the followingareas shall be made and retained for thelife of the plant:a. Records and drawings detailing plant

design changes and modifications madeto systems and equipment as describedin 5.3,3,F.S.

5-16 Rev.4 7/28f75

b. Records of gll environmental surveillancedata.

c. Records to demonstrate compliance withthe limiting conditions in Section 2.

5.7.2 All other records and logs relating to theenvironmental technical specifications shallbe retained for five years following loggingor recording. These shall include (but arenot limited to) the following:a. Details or any abnormal operating

conditions having an effect on. theenvironment, and actions taken tocorrect those conditions.

b. Maintenance activities to environmentmonitoring equipment, including butnot limited to:

P.)(31

routine maintenance and componentreplacement,equipment failures,replacement of principal itemsof equipment„

ci Records of radioactivity levels inliquid and gaseous wastes released tothe environment.

d. All reviews, including actions takeand reasons therefore, required inSections 2, 3, and 4 of this specification.

5-17 Rev. 4 7/28/75

:

6.0 SPECIAL CONDITIONS

6.1 Li ht Screen to Minimize Turtle DisorientationAustralian pine or other suitable plants (i.e,,native vegetation such as live oak, native figs,wild tamarind, and others) shall be planted, asa light screen, along the beach dune line borderingthe. plant property to minimize turtle disorientation.

6-1 Rev. 4 7/28/75

x~ " ~ P

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h

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