ML18113A483

Florida Power & Light, Chemistry Department Letter of Instruction CC-04 Revision 0

ML18113A483
Person / Time
Site:	Saint Lucie
Issue date:	07/28/1975
From:	- No Known Affiliation
To:
References
Download: ML18113A483 (67)

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FMRIDA POLiER 6 LIQlT COoPALL ST. LUCIE PLANT C1lF" HSTF.Y DHPART'ENT IETTER OF INSTRUCTION CC-04 REVISION 0

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l. 0 Tia1c ') i D., TFP'll N.'ION OF .II"1~02c Rr.CIRCIfLPTIO" .TDES FOR RZPP" SEXTATIVE SAF1PL) at'G, 2, 0 ~Aotova1:

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<<tier Lv'.tE iW',If'.S~tlrp IIIIIILL Date to bc Re ii I

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J. To Qstablish .in+'aura recirculation ti~es .or various tan'ks to reach equilibriu~a a'ter che vocal'hanges are made, 3.R To establS.sh nininiu~ times for recirculation fprior to sampling tanks w order to assure representative sanplca. Certain tanks and syste. s have concentration lie=its required by technical specificat ons, ex. Boric Acid Haieup Tanks. Also Regulatory Guide la21 states that large volu=ies of liquid waste should be piggy in as short a t,i"..e as possible to assure sedi'cnts and particu3utes are uniiormlp distributed prior to sa=pling. ~ ~

400 IilSCYVCC3.0nS a listed io T alee I i1l 4e cb"8'eA For xengcugntgo>

4.X Ql tanks.

tines d urxnp r'he Ta s-artup I

x proran as fol3.o's:

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7 4 c 1.1 ZiI1 tank to

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2 V@kc che:"ichl a >tron d~'t oa to tank. (Chc=istry Depart ent and specific chca~cal J.

Supervisor shoulld d cc idcc a"ount to bc used r )

through noaaaI recirculation path.

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Sanplc tank untx I equilibriu~

is reached (frequency to 4.1. d cntt on tank size and floe rare),

be der.ernincd dcpcn d wct layup conditions of CC-03 4.1.5 Drain and xc f iII tan.k to 0

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Pg. 2 of 4 LETTER OF IhSTR JCTXO'8 CC 0 l ~ REVISION 0 CO~l{'UTATIOa) 01'11.'$l:3:;f. RcC:PC% 'aTION TOMS kM PKPRESLNTATD'E SAiPLl hC 4,0 Instructions: (Cont.)

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

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

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TABLE X Boric Acid Condensate Tanks

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Vastc Condcnsntc Tan's CVCS )iold-Up Tanks 3A, 19, 1C, lD I

Boric Acid iiolding Tank Equip"..ent Drain Tank Chemical Drain Tank Laundry Drain Tanks Refueling Pater Storage Tank Boric Acid Hakeup Tanks

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LETTKR OF INSTFUCTIO'8 CC"04; REVXSXO'A 0 CO<<IEPUTATIOli Or <<G'sl:.:U';E RECIRCUUlTIOiE TL~KS B)R REPOSE'iTATXVE SAiPLXNG.

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VGLVhi TANK'R..CIRCU1 ETIO!a DATA 8HZ 7 rC a(~? LWSA.F.

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CRXPTXO:l'F FJ.Otll FATH p(~ @ra!ry g (r~ra(i CHBGCQ TO BE Q)DW PiirS 6 Ak.! 5 i,

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DATE PERPPP'aD PEP@'PPg:-:P ET

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.'IIEIIISTRY ar

TABLE OF CONTENTS P acae 1.0 DEFINITIONS 1.1 National power emergency 1>>1 1.2 A regional emergency 1-1 1.3 1.4 Reactor emergency Circulating water system l-l 1-1 1.5 Frequency definitions follow 1-1 1.6 Total Residual Chlorine 1-2 1.7 Intake Temperature 1-2 1.8 Discharge Temperature 1-2 1.9 Dissolved Oxygen 1<<2

1. 10 Limiting Conditions 1-2

l. 11 'Salinity 1-2 1-2 1.12 Continuous Recording 1.13 Channel Calibration 1-2 1.14 Channel Functional Test 1>>3 1,15 Batch Releases 1-3 1.16 Continuous Release 1-3 2.0 LIMITING CONDITIONS 2-1 General 2.1 Thermal 2~2 r

2..1.1. Maximum Discharge 'Temper'ature 2~2 Maximum Condenser Temperature Rise 2-3

'.1.2 2 ~ 2. Chemical 2-3 2.2.1 Biocides 2.2.2 pH 2.4 Radioactive Effluents 2-5 2.4. 1 Liquid Effluents 2-.5 2.4.2 Liquid Naste Sampling and Monitoring 2-6 2.4.3 Gaseous Naste Effluents 2<<10 2.4.4 Gaseous Waste Sampling and Monitoring 2-13

2. 4'.5 Solid Waste Handling and Disposal 2-16 3.0 ENVIRONMENTAL SURVEILLANCE 3-1 3.1 Non-Radiological Surveillance 3<<1 3.1.A ABIOTXC 3-1 3,1,A,1 Biocides 3-1 3.1.A.2 Heavy Metals 3-1

3. 1.A. 3 pH 3-2

3. 1.A.4 Dissolved Oxygen 3-2 i Rev. 4 7/28/75

TABLE OF CONTENTS (Continued)

Pacae 3.1.A.5 Salinity 3-2 3.1.A.6 Temperature 3-3 3.1.'B BIOTIC 3-4 a) Benthic Organisms 3-4 b) Plankton 3-4 c) Nektonic Organisms 3-4 d) Macrophytes 3-4 e) Water Quality 3-4 f) Migratory Sea Turtles 3-5 3.2 Radiological Environmental Monitoring 3-6 3.3 Onsite Meteorological Monitoring 3-18 4o 0 SPECIAL SURVEILLANCE 6 SPECIAL STUDY ACTIVITIES 4-1

4. 1 Entrainment of Aquatic Organisms 4-1 4.2 Impingement of Aquatic Organisms 4-1 4.3 Minimum Effective Chlorine Usage 4-2 5, 0 ADMINISTRATIVE CONTROLS 5-1 5.1 Responsibility 5-1 5.2 Organization 5-1 5.3 Review and Audit 5-1 5.4 Action To Be Takne If A Limiting 5>>4 Condition Is Exceeded

'5.5 Procedures 5-5 5.6 Reporting Requirements 5-5 5.6.1 Routine Reports 5-5 5.6.2 Non Routine Reports 5-14 5.6.3 Changes in Environmental 5-16 Technical Specifications 5.7 Records Retention 5-16 6.0 SPECIAL CONDITIONS 6.1 Light Screen to Minimize Turtle 6-1 Disorientation Rev. 4. 7/28/75

TABLE OF CONTENTS (Continued)

TABLES Pacae Table 2.4.1 Radioactive Liquid Sampling Analysis 2-17 "Table 2.4.2 Radioactive Gaseous Waste Sampling and 2-19, Analysis Table 2.4.3 'Liquid Waste System Monitors and 2-20 Samplers Table 2.4.4 Gaseous Waste System Monitors and 2-21 Samplers Table 2.4.5 Gamma and Beta Dose Factors 2-22 Table 3.2-1 Operational Environmental 3-9 Radiological Surveillance Program Sampling Locations Table 3. 2-2 Operational Environmental Radiological 3-14 Surveillance Program t Table Table 3.2-3 5.6.1-1'able 5.6.1-A Detection Capabilities Effluent and Waste Disposal Gaseous Effluents Summation of All Releases 3-17 5-7 5-9 Table 5.6.1-B Gaseous Effluents 5-10 Table 5. 6. 1-C Liquid Effluents - Summation 5-11 of All Releases Table 5.6.1-D Liquid Effluents 5-12 Table 5.6.1-E Solid Waste and Irradiated 5-13 Fuel Shipments Rev. 4 7/28/75

TABLE OF CONTENTS (Continued)

FIGURES Pacae Figure 3.2-1 Operational Radiological 3-12 Surveillance Sampling Stations Figure 3.2-2 Inset to Figure 3.2-1 3-13 Figure 5. 2-1 FP&L Corporate Organization 5-2 Environmental Affairs iv Rev 4. 7/28/75

1,6 Total Residual Chlorine The amount of free and combined available chlorine present in water.

1.7 Intake Tem erature The temperature of the cooling water as measured at the plant intake structure.

1,8 Dischar e Tem erature The temperature of the cooling water as measured near 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 effluents and operating practices which may have an adverse impact. on the environment.

1. 11 ~Salin it The total amount of solid material in grams contained. in one killogram of sea water when all the carbonate has been converted to oxide, the bromine and, iodine replaced .by chlorine, and organic. matter completely oxidized.

1,12 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 successive printing of the same parameter.

1.13 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.

Rev. 4 7/28/7S

1. 14 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.

1.15 Batch Releases Discontinuous release of gaseous or liquid effluent which takes place over a finite period of time, usually hours or days.

1,16 Continuous Release Release of gaseous or liquid effluent which is essentially uninterrupted for extended periods during 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 stress to the aquatic ecosystem by limiting the temperature rise in the 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 the Atlantic Ocean shall be limited to a maximum of ill'F and shall not, cause a temperature rise in excess of 1.5'F above ambient surface temperature outside a 400 ~ere zone of mixing during the months of June through September, nor a O'F rise during the remaining months. Zn addition, the

.surface temperature conditions within the zone of mixing shall not exceed a rise of 5.5'F over ambient temperature nor a maximum temperature of 93 F as an instantaneous maximum at any point.

Thermal defouling. of the intake pipeline is allowed subject to a maximum release temperature of 120'F, and a maximum sur face temperature rise o f 2'F.

Under the following conditions, which may be expected to cause 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 of chlorine; 3) . ouling o f circulating water system.

Temporary transients due to accidental loss of c'rculating water system components may cause temperature rises in excess of limitations stated above'. Variances due to the. e transients shall be limited to no more than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per month.

Monitorin Requirement:

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

continuous temperature monitoring station located within 500 feet from the pr'mary monitoring device, shall be used as a backup system if the primary system fails. Xn this event this station "hall be checke"'very 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until the primary system is restored. See section 3.1.A.6 for complete details of the monitoring program.

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

2, 1. 2 - Maximum Condenser Tem erature Rise Under normal full power operation, the temperature rise across the condenser shal'1, not exceed. 26'F. Under the

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following conditions, the condenser temperature 'rise shall not exceed 35'F: 1) Condenser and/or circulating water pump maintenance; 2) Throttling circulating water pumps to minimize use of chlorine; 3) Fouling of circulating water system.

Bases:

The limitations provide reasonable assurance that the overall aquatic ecosystem in the area of the thermal plume w'ill experience an acceptable environmental impact. The placement of the temperature monitoring instrument in the discharge canal will give the temperature of the discharge water before mixing with the receiving water.

2.2 CHEMICAL

~b'he 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 discharge due to operation of the plant, (3) to assure that continued multiple use o the receiving waters by human populations is protected, and (4) to control the quality of the receiving medium.

2.2.1 Biocides otal Residual Chlorine at the downstream end of the discharge canal shall not exceed o.2 mg/1 on an average for a chlorination addition period. If this level is exceeded, adjustments to the injection system shall be made to reduce the concentration, and each suceedi.'ng chlorination period shall be monitored until the concen-tration is within the specification. Chlorine shall be added for less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per day.

Monitorin Requiremen'ts:

A grab sample of condenser cooling. water shall taken weekly in the discharge canal and analyzedbe for total residual chlorine. The samples shall be taken during the period of chlorination. The time of be-ginning the chlorination and when the sample was taken shall be logged.

2-3 Rev. 4 7/28/75

Bases:

~8hen injected, chlorine is diluted by the coolin'g water and consumed in the process of controlling slime. To be sure that enougn 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 impact.

2.2.2 pH The pH of the cooling water in the discharge canal shall not be less than 6,0 nor greater than 9.0 pH units.

P Monitorin Re uirement:

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

Basis:

The pH limits set forth will provide reasonable assurance of an acceptable environmental impact when 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 controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures.

The concentration of radioactive materials in effluents shall be within the limits specified in 10 CFR Part 20.

To ensure that the releases of radioactive material above background to unrestricted areas be as low as practicable as defined in Appendix I to 10 CFR Part 50, the following design objectives apply:

For liquid wastes:

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

b. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases,.

discharged from each, reactor should not exceed 5 Ci.

For gaseous 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 than 10 mrad; and an annual air dose due to beta radia-tion of less than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the boundary of the site.

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

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

2.4.1. Li uid Waste Effluents

a. The concentration of radioactive materials released in 2-5 Rev. 4 7/28/75

"liquid waste effluents from all reactors at the site shall not exceed the value specified in 10 CFR Part 20, Appendix B, Table XI, Column 2, for unrestricted areas.

b. The cumulative release of radioactive materials, in liquid waste effluent excluding tritium and dissolved gases, shall not exceed 10 Ci/reactor/calendar quarter.

c ~ The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci/reactor in any 12 con-secutive months'.

d. During release of radioactive wastes, the effluent con-trol monitor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.4.l.a above, except as provided in 2.4.2.d below.

e. The operability of each automatic isolation valve in the liquid radwaste discharge lines shall be demon-strated quarterly.

The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their dis-charge when the projected cumulative release could exceed 1.25 Ci/reactor/calendar quarter, excluding tritium and dissolved gases.

go The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the

. environs shall not exceed 10 Ci, excluding tritium and dissolved gases.

h. Xf the cumulative release of radioactive materials in liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 Ci/reactor/calandar quarter, the licensee shall make an investigation to identify the causes for such releases, define and initiate a program of action to reduce such releases to 'the design objective levels listed in Section 2.4, and report these actions to the NRC 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 0.5 curies requires notification. This notification shall be 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 radioactive concentration and volume before dilution of liquid.

waste intended for discharge and the average dilution flow and length of time over which each discharge occurred. Sample analysis results and other reports shall be submitted as required by Section 5.6.1 Specifications. Estimates of the sampling and of'hese analytical errors associated with each reported value shall be included.

2-6 Rev. 4 7/28/75

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

for the concentration of each significant gama energy peak in accordance with Table 2.4-1 to demonstrate compliance with Specification 2.4.1 using the flow rate into which the waste is discharged during the period. of discharge.

When operational or other type of limitations pre-clude specific gamma radionuclide analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive material released in the batch. A weekly sample, composited from proportional aliquots from each batch released during the week, shall be analyzed for the principal gamma-emitting radionuclides.

co Sampling and analysis of liquid radioactive waste shall be performed in accordance with Table 2.4-1. Plant Procedures shall be developed to ensure samples taken from liquid batches for release to the environment are representative of the activity actually released.

d. The radioactivity in liquid wastes shall be continuously monitored and recorded during release. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be dis-charged shall be analyzed and two plant personnel shall independently check valving prior to the discharge. Xf these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a liquid waste tank shall be made and any release in progress shall be terminated.

e. The flow rate of liquid radioactive waste shall be con-tinuously measured and recorded during release. Xf the flow monitors are inoperable prior to a release, it shall be determined prior to the release, that even at the maximum design flow rate of the system, applicable activity release limits will not be exceeded.

All liquid effluent radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Stan-dards source. Each monitor shall also have a functional test monthly and an instrument check prior to making a release.

gi The radioactivity in steam generator blowdown shall be continuously monitored arid. recorded. With one .steam generator monitor inoperable, the sampling system shall be realigned so that the operable monitor is receiving flow from both steam generators. Whenever both monitors are inoperable, the blowdown flow shall be diverted to the waste management system and the direct release to the environment terminated.

2-7 Rev. 4 7/28/75

Bases: The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance .that the resulting annual dose to the total body or any organ of an individual in an unrestricted area will not exceed 5 mrem. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a depen-dable source of power under unusual operating conditions which may temporarily result in releases higher than the 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 flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as 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 of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and are consistent with Ap-pendix I to 10 CFR Part 50.

Specification 2.4.l.a requires the licensee to limit the concentration of radioactive materials in liquid waste effluents released from the site to levels speci-fied, in 10 CFR Part 20, Appendix B, Table II, Column unrestricted areas. This specification provides 2,'or assurance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Com-mission's Regulations.

Specifications 2.4.l.b and 2.4.l.c establish the upper limits for the release of radioactive materials in liquid effluents. The intent of these Specifications is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power'nder unusual operating conditions which may temporarily result in releases 'higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed. Releases of up to these levels will result in concentrations of radioactive material in liquid waste effluents at small percentages of the limits specified in 10 CFR Part. 20.

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 to control and monitor the releases of radioactive materials in liquid wastes during any period that these releases are taking place.

Specification 2.4.l.f requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quan-tity released will not exceed the design objective. In order to keep releases of radioactive materials as low as practicable, the specification requires operation of equipment whenever it appears that the projected cumula-tive discharge rate will exceed one-fourth of this design objective annual quantity during any calendar quarter.

Specification 2.4.l.g restricts the amount of radioactive material that could be inadvertently released to the en-vironment to an amount that will not exceed the Technical Specification limit.

In addition to limiting conditions for operation listed under Specifications 2.4.1.b and 2.4.1.c, the reporting

-requirements of Specification 2.4.l.h delineate that the licensee shall identify the cause whenever the cumulative release of radioactive materials in liquid waste effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design ob-jective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred as required by Specification 5.6.2 of these Technical Specifications.

Specification 2.4.l.i provides for reporting spillage or release events which, while below the limits of 10 CFR Part 20, could result in releases higher than the design objectives.

The sampling and monitoring requirements given under Specification 2.4.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive 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 furnished to the Commission according to Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

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

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

subscript v, refers to vent releases subscript i, refers to individual noble gas nuclide (Refer to Table 2.4-5 for the noble gas nuclides considered)

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

ZQi sum of the individual noble gas radio-nuclides determined to be present by isotopic analysis K = the average total body dose factor due to gamma emission (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 determined each time isotopic analysis is required as delineated in Specification 2.4.4. Determine the following using the results of the noble gas radionuclide analysis:

K = (1/ T) EQj.Ki 3.

L = (1/QT) EQiLi 3.

M = (1/QT) EQiMi 3:

N = (1/QT) EQiNj.

3.

where the values of Kj I Lj I Mj and Ni are provided in 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 radioiodines and radioactive materials in particulate forms with half-lives greater than eight days.

a ~ The release rate limit of noble gases from the site shall be such that 2.0 QTvKv < 1 and QTv( v + 1.1Nv) 1 (2) The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site shall be such that 5.5 x 10 Qv

b. (1) The average release rate of noble gases from the site during any calendar quarter shall be such that QTv v and 6 3 QTv~v (2) The average release rate of gases from the site during any 12 consecutive months shall be 25 QTvNv 1 and 13 QTvMv 1 (3) The average release rate per site of all radio-iodines and radioactive materials in particulate form with half-lives greater than eight, days during any calendar quarter shall be such that 13 5.5x10 Qv 1 (4) The average release rate per site of all radio-iodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall 2-11 Rev. 4 7/28/75

be such that 25 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 period of 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 Section 2.4 and report these actions to the NRC within 30 days from the end of the quarter during which the releases occurred.

(1) If the average release rate of noble gases from the site during any calendar quarter is such that 0 QTvNv 1 or Tv v (2) If the average release rate per s'ite of all radio-iodines and radioactive materials in particulate form with half-lives greater than eight days during

.any calendar quarter is such that 50 5.5 103 Q.

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

d. During the release of gaseous wastes from the gas decay tanks, the gaseous discharge monitor shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.4.3.a above. Whenever this monitor is inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each gas decay tank to be discharged shall be analyzed and two plant per-sonnel shall independently check valving prior to the discharge. If this monitor is inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a gas decay tank shall be made and any release in progress shall be terminated. The operability of each automatic isola-tion valve shall be demonstrated quarterly.

e. The maximum activity to be contained in one waste gas storage 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 15 curies of noble gas or 0.02 curie of radioiodine in gaseous form requires notification. This notification shall 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 the sampling and analyses results shall be submitted in accordance 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 the turbine building ventilation exhaust and as noted in Specification 2.4.4.c, shall continuously monitored for gross radioactivity and the flow continuously measured and recorded. Whenever these monitors are inoperable, grab 'samples shall be taken and analyzed daily for gross radioactivity. Xf these monitors are inoperable for more than seven days, these releases shall be terminated.

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

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

e. Sampling and analysis of radioactive material in gaseous waste, including particulate forms and radioiodines shall be performed in accordance, with Table 2.4-2.

N Bases: The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practical in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual air dose from the site due to gamma radiation will not exceed 10 mrad, and an annual air dose from the site due to beta radiation will not exceed 20 mrad from noble gases, that no individual in an unrestricted area will receive an annual dose to the total body greater than 5 mrem or an annual skin dose greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual from radioiodines and radioactive material in particulate form with half-lives greater 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 of health and safety, to assure that the public is provided with a dependable source of power'nder unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the con-centration limits specified in 10 CFR Part 20. Even with this operational flexibility under, unusual operating condi-tions, if the licensee exerts every effort to keep levels of radioactive material in gaseous waste effluents as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

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

Specification 2.4.3.a(1) limits the release rate of noble gases from the site so that the corresponding annual gamma and beta dose rate above background to an individual in an unrestricted area will not exceed 500 mrem to the total body or 3000 mrem to the skin in compliance with the limits of 10 CFR Part 20.

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

Dose calculations have been made to determine the site boundary locatio'n with the highest anticipated dose rate from noble gases using on-site meteorological data and the dose expressions provided in Draft Regulatory Guide 1.AA.

The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclides.

The offsite location with the highest anticipated annual dose from released noble gases is 1600 meters in the North direction.

The release rate Specifications for a radioiodine and radio-active material in particulate form with half-lives greater than 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 airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent'consumption by man, and

3) deposition onto grassy areas where milch animals graze with consumption of,the milk by man. Methods for estimating doses to the thyroid via these pathways are described in Draft Regulatory Guide 1.AA. The offsite location with the highest anticipated thyroid dose rate from radioiodines and 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 the release rate of radioiodines and radioactive material in particulate form with half-lives greater than eight days so that the corresponding annual thyroid dose via the most restrictive pathway is less than 1500 mrem.

For radioiodines and radioactive material in particulate form with half-lives greater than eight days, the most restrictive location 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 for the releases of noble gases and radioiodines and radioactive material in particulate form with half-lives greater than eight days at twice the design objective annual quantity during any calendar quarter, or four times the design ob-jective annual quantity during any period of 12 consecutive months. In addition to the limiting conditions for operation of 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 exceeds one-half the design objective annual quantity during any calendar quarter and that the proposed program of action to reduce such release rates to the design objectives shall be described.

Specification 2.4.3.d requires that suitable equipment. to monitor and control the radioactive gaseous releases are operating 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 instantaneous ground release, a X/Q based 5 percent. meteorology, the average gross energy is 0.19~.Mev per disintegration (consi-dering Xe-133 to be the principal emitter) and exposure occurring at the minimum site boundary radius using a semi-infinite cloud model. The calculated quantity will limit the offsite d'ose above background to 0.5. rem or less, consistent with Commission guidelines.

2-15 Rev. 4 7/28/75

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

The sampling and monitoring requirements given under Speci-fication 2.4.4 provide assurance that radioactive materials released in gaseous waste effluents are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. These requirements provide the data for the, licensee and the Commission to evaluate the plant's per-formance relative to radioactive waste effluents released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of Section 5.6.1 of these Technical Specifications. On the basis of such reports and any addi-tional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appro-priate.

The points of release to the environment to be monitored in Section 2.4.4 include all the monitored release points as provided for in Table 2.4-4.

Specification 2.4.4.b excludes monitoring the turbine building ventilation exhaust since this release is expected to be a negligible release point. Many PWR reactors do not have turbine building enclosures. 'To be consistent in this re-quirement for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required.

2.4.5 Solid Waste Handlin and Dis osal

a. 'easurements shall be made to determine or estimate the total 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 handling and disposal given under Specification 2.4.5 provide assurance that solid radioactive materials stored at the plant and shipped offsite are packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 170-178.

2-16 Rev. 4 7/28y75

TABLE 2.4-1 RADIOACTIVE LIQUID SAMPLING AND ANALySIS Detectable Liquid Sampling Type of Concentrations Source Fre uenc ctivity Anal sis (gCi/ml)

.72 A. Monitor Tank Releases Each Batch rincipal Gamma Emitters 7 5 x 10' 6

One batch/Month issolved Gases 10 3 10" Weekly Composite a-La-140,I-131

.3 Monthly Composite 10

-7 10-'

r'oss 6

.-3 uarterl Com osite 3 r-90, Sr-89 5 x 10

- -7 B. Steam Generator Principal Gamma Emitters 5 x 10 Blowdown4 eekly 5,7,8 a-La-140, I-131 10 3 6 One Sample/Month 4 issolved Gases 10 5

onthly Composite -3 10 Gross a 10'3 I

I Quarterly Composite 5lSr-90, Sr-89 5 x 10 1

The detectability limits for activity analysis are based on the technical feasibility 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 are measured below the stored limits, they should also be reported.

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 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 to the quantity of liquid waste discharged.

Required only when activity is detected in the Steam Generators by routine analysis or Steam Generator'lowdown monitor and blow down discharge to the circulating water system is in progress.

To be representative of the average quantities and concentrations of radioactive t~

materials 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 composite should be throughly mixed in order for the composite sample to be representative of the average effluent release.

2-17 Rev. 4 7/28/75

6 For dissolved noble gases in water, assume a MPC of 4 x 10 5 pCi/ml of water.

When operational or other type of limitations preclude specific gamma spectrum analysis of each tank, gross activity measurements shall be made to estimate the quantity and concentration of radioactive material released in the batch. A week-ly sample composited from proportional aliquots from each batch released during the 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 2.4-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Sampling Type of Detectable Source Frequency Activity Analysis Concentrgtion (pCi/ml) 42 A. Waste Gas Decay Tank: Each Tank Princi al Gamma Emitters 10 .

Releases H-3 10-6 3

B. Containment Purge Each Purge Princi al Gama Emitters 10 Releases H-3 10 Monthly5,6 42g3 C. Condenser Air Ejector Principal Gamma Emitters 10 .

H-3 10 42i3 D. Environmental Release Monthly Princi al Gamma Emitters 10 Points (Gas Samples)

H-3 10 I-131 -12 Weekly (Charcoal 1 Sam le)

Monthly (Charcoal I-133,I-135 10-10 Sam le)

Weekly (Particulates) Principal Gamma Emitters 10- 1 (at least for Ba-La-140; I-131)

Monthly Composite4 (Particulates)

-11 Gross a 1

-11 Quarterly Composite 4 Sr-90, Sr-89 1 (Particulates) 1 detectability limits for activity and analysis are based on technical feasi-II The above 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 radionuclides at. levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to cal-culate the levels of such radionuclides using observed ratios with those radionuclides which 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, materials in 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 or by the secondary side process monitors.

No sampling required if unit is shutdown during the sampling intexval.

2-19 Rev. 4 7/28/75

TABLE 2.4-3 ST. LUCIE PLANT LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS AUTO CONTROL GRAB MEASUREMENT HIGH LIQ-.

PROCESS STREAM OR RADIATION TO ISOLATION CONTINUOUS SAMPLE GROSS DISSOLVED ISOTOPIC UID LEVEL RELEASE POINT ALPHA H-3 ALARM VALVE MONITOR STATION ACTIVITY GASSES ANALYSIS ALARM EQUIPMENT DRAIN TANKS CHEMICAL DRAIN TANKS LAUNDRY: 'RAIN TANKS LIQUID RADWASTE DISCHARGE PIPE S/G BLOWDOWN SYSTEM X OUTDOOR STORAGE TANKS (POTENTIALLY =-

RADIOACTIVE)

COMPONENT COOLING SYSTEM X

TABLE 2.4-4 ST. LUCIE"PLANT . GASEOUS WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS AUTO CONTROL GRAB MEASUREMENT PROCESS STREAM OR TO ISOLATION CONTINUOUS SAMPLE RELEASE POINT VALVE MONITOR STATION NOBLE GAS I PARTICULATE H-3 GAS DECAY TANK EFFLUENT X -

X X X CONDENSER AIR EJECTOR X X X BUILDING VENTILATED SYSTEMS PLANT VENT X X FUEL HANDLING AND X X STORAGE BUILDING

TABLE 2.4-5 GAMMA AND BETA DOSE FACTORS FOR ST LUCIE PLANT g UNIT 1

-6 3 X/Q = 2,1 x 10 sec/m DOSE FACTORS FOR VENT.

K. L. M N.

NOBLE GAS av iV iV iV RADIONUCLIDE Total Body Skin Beta Air Gamma Air rem/yr rem/yr rad/yr'i/sec

~rad/ r Ci/sec Ci/sec Ci/sec Kr-83m 5.8 x 10 0 0.6 0. 028 Kr-85m 0.88 3.1 4.1 0. 92 Kr-85 0. 014 2.8 4,1 0. 015 Kr-87 1.9 20 22 2.0 Kr-88 6.0 5.0 6.2 6.3 Kr-89 0,5 21 22 0.52 Xe-131m 0.4 1.0 2.3 0.5 Xe-133m 0.3 2.1 3.1 0. 41 Xe-133 0. 36 0. 64 2.2 0. 45 Xe-135m 0.64 1.5 1.6 0.68 Xe-135 1.5 3.9 5.2 1.6 Xe-137 0. 072 26 27 0. 076 S

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

PWR Unplanned or Uncontrolled Release Report. Any unplanned or uncontrolled offsite release of radioactive materials in excess of 0.5 Curie in liquid or in excess of 15 Curies of noble gases or 0.02 Curie of radioiodines in gaseous form requires notifi-cation. This notification must be made by a written report within 30 days to the NRC. The report shall describe the event, identify the causes of the unplanned or uncontrolled release and report 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 Total Residual Chlorine in the discharg canal to insure that no adverse impact on the environment is occurring.

S ecification Total Residual Chlorine shall be mcnitored in the discharge canal on a weekly basis while a condenser

.section is being chlorinated. See Section 2.2.1 for limiting conditions. t Re ortin Re uirement

,Total Residual Chlorine 'concentration shall be reported in the Annual Environmental Operating Report.

Ob 'ective The purpose of this study is;to monitor heavy metals concentrations in the intake and discharge canals to detect any measurable increase in heavy metals.

S ecification Grab samples shall be taken on a monthly'asis at the intake and discharge canals and analyzed for Mercury, Arsenic, Chromium, Copper, Iron, Lead, Nickel, and Zinc.

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

3-1 Rev. 4 7/28/75

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. A study shall be conducted to determine the effects of the discharge thermal plume on turtle nesting patterns and turtle migration. In addition, control studies

'atchli:ng on temperature stress,'atching, and rearing factors will be conducted using turtle eggs from displaced nests.

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

Florida Power & Light will review the data after two years of plant operation. ,If effects attributable to the plant are found acceptable, the results shall be 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 reported in the Annual Environmental Operating Report.

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

3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING The Operational Radiological Environmental Surveillance Program is conducted to measure radiation levels and radioactivity in the environs, and to assist in verify-ing any projected or anticipated radioactivity release resulting from plant operations which could bring about public exposure to radiation.

S ecifications 3.2.a Environmental samples shall be collected at the designated locations shown in TABLE 3.2-.1 and FIGURES 3.2-.1 and 3.2-.2.

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

Direct, radiation shall be measured by thermolumine-scence dosimetry (TLD) at locations. shown in TABLE 3.2-1 and FIGURES 3.2-1 and 3.2-2. The system shall be capable of measuring 25.8 mrad/year at the 90%

confidence level based on a quarterly collection frequency.

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

3.2.d A census of gardens producing fresh leafy vegetation for human consumption shall be conducted near the end of the growing season to determine their location with respect to the plant site. This census is limited 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 equivalent counting technique.

2) If no milk-producing animals are located in the vicinity of the site, as determined by Specification (e) below, the census described in item (1) above,'hall be extended to a distance of 5 miles from the site.

3) If this census reveals the existence of a garden at a location yielding a calculated thyroid dose greater than that from a previously sampled garden, the new location shall replace the garden previously having the 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 dropped from the surveillance program after notifying NRC in writing that such vegetables are no longer grown at that location.

3.2. e A census of animals producing milk for human consumption shall be conducted semiannually to determine their location and number with respect to the plant site. The census shall be conducted under the following conditions:

1) Within a 1 mile radius from the plant site or within a 15 mrem/year isodose line (as calculated using dose models presented in Regulatory Guide 1. 42), whichever is larger, enumeration by a door-to door or equivalent counting technique.

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

If it is determined from the census that animals are present at a location which'ields a calculated thyroid dose greater than that from previously sampled animals, the new location shall be added to the surveillance program as soon as practicable.

The sampling location having the lowest calculated dose may be dropped from the surveillance program 3 months after sampling begins at the new location.,

Also, any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying NRC in writing that milk-producing animals are no longer present at that location.

3.2. f Deviations from the required sampling schedule are permitted if specimens are not obtainable due to hazardous conditions, seasonal unavailability, or.

malfunction of automatic sampling equipment. In the latter case, every reasonable effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the'ampling schedule shall be described in the annual report.

A deviation of not greater than one week from the required frequency of analysis for grass beta activity, as shown in TABLE 3.2-2, is permitted equipment failure delays the analyses, Every if reasonable effort shall be made to effect expeditions equipment repair.

Re ortin All required reports from this Operational Radiological Environmental Surveillance Program shall be prepared and presented in the manner described in Section 5.6.1.B of these 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 levels in the air, water and land environment which may be attributed to the operation of the plant. The methods, procedures and techniques used were developed during the preoperational phase and have provided background measurements that will be used as a base for distinguishing significant 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 Station No. Descri tion B~earin

• Distance* Vector Sam led H03 Meadowbrook Dairy, Glades Cut-of f Ro'ad, 260 22. 526 km Milk St. Lucie County (14. 00 mi)

H08 Florida Power & Light Company Substa- 293 9. 170 km Soil, Air Particulates & Iodine, tion White City, Weatherby Road west (5.7 mi) .

Direct Radiation of U. S. 1 H09 Florida Power & L'ight Company Substa- 196 11.745 km Soil, Air Particulates & Iodine, tion west of U.S. 1, just south of (7.30 mi) Direct Radiation St. Lucie County Line H10 Indian. River Field Laboratory, Univer- 300 19.308 km Food Crops (Citrus), Air Particulatesh sity of Florida, west of SR 713 (12.00 mi) Iodine, Direction Radiation, Soil Hll City of Ft. Pierce, Water System 323 14.480 km Potable Water (Well) City of Ft.

Collected at St. Lucie County Health (9 mi) Pier'ce Department, Ave., *"C", Ft. P'ierce H12 Florida Power & Light Company Substa- 180 19.308 km Potable Water (Well) City of Stuart, tion SR 76 west of U.S. 1, Stuart, (12.00 mi) Air Particulates & Iodine, Direct Martin County Radiation

~ H13 On Site, Point north of Big Mud Creek 312 1021 m Surface Water, Bottom Sediment at Indian River (0. 63 mi) (Estaurine)

TABLE 3.2-1 (Continued)

Station Descri tion B~earin

• Distances Vector Sam led No.

H14 Employees Parking Lot, southeast of 160 503 m Air Particulates & Iodine, Direct Containment (0.31 mi) Radiation 0

H15 On Site, Beach near Discharge Structure 89 808 m Ocean Water & Bottom Sediment, (0,.50 mi) Aquatic Biota H16 Beach (ocean) opposite Blind Creek 31 1509 m Ocean Bottom Sediment, Beach Sand (0.94 mi)

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

H22 Lentz Groves, U.S. 1 210 8.849 km (5.50 mi)

'ood Crop (Citrus)

H23 Montauk Groves, U.S. 1, south of 270 7.562 km Food Crop (Citrus),

Easy Street (4. 70 mi)

H24 Poster Groves, U.S. 1, north of 300 8.608 km Food Crop (Citrus)

Tumblin Kling Road (5. 35 mi)

H25 Childs Groves, Bell Avenue, west of 297 11. 263 km Food Crop (Citrus)

Sunrise Blvd. (7. 00 mi)

I~

H26 Wouters Groves, west of SR 713 on .314 21.720 km Food Crop (Citrus)

Immokola Road (13.50 mi)

H30 Residence, 7609 Indian River Drive 245 3. 218 km Ground Water (Well), Soil, Air (2.00 mi) Particulates & Iodine, Direct

~] Radiation

TABLE 3, 2-1 (Continued)

'I Station No. Descri tion Bearing* Distance* Vector Sam led H31 North Port St. Lucie Water System, 250 10.619 km Potable Water (Well) Port.

Prima Vista Blvd. (6.60 mi) St. Lucie H32 Department of Health and Rehabilit- 338o 30.571 km Aquatic Biota, Ocean Water 6 ative Services Entomology Laboratory, (19.00 mi) Bottom Sediment, Air Particulates East of U.S. 1, Vero Beach 6 Iodine, '.Soil, Direct Radiation, Beach Sand H33 On Site, between Canals, east of AIA 138o 945 m Air Particulates 5 Iodine, Direct (0. 59 mi) Radiation H34 On Site, Meteorological Tower 27 762 m Air Particulates 6 Iodine, Direct (0.47 mi) Radiation l

H36 On Site, Discharge Canal west of AIA 101 305 m . Surface Water, Bottom Sediment (0,19 mi)

H39 Vista Royal Condominium, 1 mile north 338o 32.180 km Food Crop (Citrus) of H32, east of U.S. 1, Vero Beach (20,00 mi)

H40 Florida Milk Shed Milk

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-'III SURVEILLANCE OT. LII as Ii .r ST. LUCIE PLANT I~

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FLORIDA

, SAMPLING LOCATIONS I~

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ST. LUCIE PLANT SAMPLING LOCATIONS B.hhl7'RoeeRv v Lwz FIGURE 3.'2-2 5'.ISO.'.FliOÃ,.,li'EACYOR Sll.E

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TABLE 3, SHEET 1 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM ST. LUCIE PLANT Exposure Pathway Collection Type and Frequency and/or Sam le Criteria and Sam lin Locations Fre uenc of Anal sis

1. AIR 1.1 Particulate and Comparison on-site versus off-site Weekly Gross Beta Iodine 6 reference locations: Gamma spectral analysis 3 locations on-site, north, east, of monthly composite a southeast of the plant: H 34, Radioactive Iodine H14, H 33 Sr-89 6 90 (Quarterly Composite) 5 locations off-site within a radius of 10 miles of plant~H 08, H 09, H 10, H 12, H 30, and 1 control location: H32 1.2 Direct Radiation Comparison of on-site versus off- Quarterly Determine direct radiation site 6 reference locations: by exposure by TLD readout 3 locations on-site, north, east, (mean of 2 TLDs) 6 southeast of the plant: H 34, H14, H33 5 locations off-site within a radius of 10 miles of plant: H 08, H 09, H 10, H 12, H 30, and 1 control location: H32

2. WATER ~ \

2.1 Surface Water 2.1.1 Discharge Canal 1 location,. west of AIAg H36 Monthly Gamma spectral analysis Tritium (Quarterly Composite)

Sr-89 s 90 (Quarterly Composite) 2.1.2 Ocean 2 locations; H15 6 H32 (Control) Monthly Gamma spectral analysis Tritium (Quarterly Composite)

Sr-89 6 90 (Quarterly Composite) 2.1.3 Estuarine 1 location; Big Mud Creek: H13 Quarterly Gamma spectral analysis Tritium 2.2 Ground Water (well) 1 location~ Residence, 7609 Indian ,Semi-annually Gamma Spectral Analysis River Drive: H30 Gross Beta Tritium

TABLE 3. SHEET 2 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM ST. LUCIE PLANT Exposure Pathway Collection Type and Frequency and/or Sam le Criteria and Sam lin Locations Fre uenc of Analysis

2. WATER (cont'd) 2.3 Potable Water 1 location, City of Ft. Pierce, Quarterly spectral analysis (wells) drinking water supply, H 1 location~ City of Stuart, ll Gamma Gross Beta Tritium drinking water supply, H 12 1 location, Port St. Lucie, drinking water supply, H 31 .

3. BOTTOM SEDIMENT 3.1 Discharge Canal 1 location< west of AIA: H36 Semi-annually Gamma spectral analysis Sr-90

3. 2 Ocean 1 location, beach west of discharge Semi-annually Gamma spectral analysis structure: H15 Sr-90 1 location, offshore, 1 mile north of discharges: H16 1 location, offshore, 1 mile south of discharge: H19 1 location, offshore, Vero Beach:

H32 -(Control) 3.3 Beach (sand) 1 location, east of Blind Creek, 1 Semi-annually Gamma spectral analysis mile north of discharge: H16 Sr-90 1 location, near intake, 1 mile south of discharge: H19 1 location, Vero Beach: H32 (Control) 3.4 Estuarine 1 location, Big Mud Creek: H13 Semi-annually Gamma spectral analysis 4.1 Crustacea 1 location, vicinity of discharge Semi-annually Gamma spectral analysis (Lobster or crab structure: H15 or shrimp) ~ . 1 location, Vero Beach: H32 (Control)

TABLE 3. SHEET 3 OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM ST. LUCIE PLANT Exposure Pathway Collection Type and Frequency and/or Sam le Criteria and Sam lin Locations Fre uenc of Analysis

4. AQUATIC BIOTA (cont'd) 4.2 Fish 4.2.1 Carnivores ,

1 location, vicinity of discharge Semi-annually Gamma spectral analysis structure: H 15 Sr-89 6 90 1 location, Vero Beach: H32 (Control) 4.2.2 Herbivores 1 location, vicinity of discharge Semi-annually Gamma spectral analysis structure: H15 Sr-89 6 90 1 location, Vero Beach: H32 (Control) 5., TERRESTRIAL

s. 1 location within 15 mile radius Semi-monthly Gamma spectral analysis of plant and in the prevailing Sr-89 wind direction from the plant: H03 6 90 1-131 1 location, Florida (state) Milk Monthly Gamma spectral analyyis Shed: H)0 (Control) Sr-89 6 90 I-131 Dairy herd census Semi-annually 5.2 Biota 5.2,1 Food Crop 6 locationsg H10g H22g H23p H24I Harvest Time Gamma spectral analysis (Citrus) H25i H26 Sr-89 a 90 5.2.2 Pood Crop 1 location as determined by garden Harvest Time Gamma spectral analysia (Edible Leafy census (Specification 3,2,d) I-131 vegetation) 5.3 Soil 5 locations within a 15 mile radius Once per 3-year Gamma spectral analysis of plant: H03, H08, H09, H10, H30. period Sr-90 1 location, Vero Beach: H32 (Control)

TABLE 3.2-3 St. Lucie Plant: Detection Ca abilities for Environmental Sam le Anal sis Media Dete"tion Capabilities*

Analysis Water Airborne Particulates F1sh i Meat Milk Vegetation Soil (pCi/1) or Gas or Poultry (pCi/1) (pCi/kg,wet) (pCi/kg,dry)

( Ci/m3) (PCi/k ,wet)

Gross beta 0.8 0. 002.

3H 199.0

. '4Mn 6.0 17.0 59 Fe 5.0 58 Co 7.0 19.0 60 7.0 20.0 65 I Zn 14. 0 39.0 89 Sr 1.6 0.005 8.0 2.0 90SSr 0.8 0.002 4.0 1.0 10.0 95 Zr-Nb 7.0 3.31 7.6 0.008 0-5 16.0 134CCs 6.0 0.008 18. 0 6.0 26.0 137CCs 7.0 0.008 18. 0 7.0 26.0 140 Ba-La 8.0 0.008 o< *Nominal: LLD's (lower limit of detection) calculated as defined in HASL-300, Rev. 8/73, pp 08-01,

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02, 03, at the 90% confidence level. The detection levels for radionuclides spectrometry- will vary according to the number of radionuclides encountered inanalyzed by gamma environmental samples.

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3'.3 ONSITE METEOROLOGICAL MONITORING Ob'ective The objective of onsite meteorological monitoring is to adequately measure and document meteorological conditions at the site, specifically at heights above ground that are represe'ntative of atmospheric conditions that exist at all effluent release points.

S ecification The onsite meteorological monitoring program shall conform to the recommendations and intent of Regulatory, Guide 1.23, Onsite Meteorolo ical Pr'o rams, and include instruments to sense wind speed and dz.rection at 33-ft and 190-ft, vertical temperature gradient between 33-ft and 200-ft, and ambient dry bulb and dewpoint temperatures at, 33-ft. he location of the meteorological tower shall be located approximately 2400 feet north of the reactor complex.

Re ortin Requirements Meteorological data shall be summar'"ed and reported in a format consistent with the recommendations of Regulatory .

Guides 1.21 and 1.23. Summaries of data and observations shall be available to the U. S. Nuclear Regulatory Commission upon request. If the outage of any meteorological instrument(s) exceeds three consecutive days,. the total outage time and dates of outage, the cause of the outage, and the instrument(s) involved sha'1 be reported within 30 days of the initial time of the outage to the U. S. Nuclear Regulatory Commission, Office of Inspection and Enforcement with a copy to the Reactor Regulation, Division of Techni'cal Review.

Office'of'uclear Any modifications to, the meteorological monitoring program as described above, or alterations of the area near the meteorological tower that would interfere w'ith the measure-ment of meteorological conditions representative of the site, shall have the written approval of the U. S. Nuclear Regulatory 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 will provide information which will be used to develop atmospheric diffusion parameters to estimate potential radiatio'n doses to the public resulting from actual routine or accidental releases of 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 on planktonic organisms of passage through the plant condensers. Specialists in the biological sub-disciplines of zooplankton. and ichthyology will perform appropriate portions of this study. Figures obtained for the intake and discharge canals will be compared to data collected at a control station.

~S ecification Samples shall be collected from the intake and discharge canals and a control station at monthly intervals when the unit is in operation to identify the organisms involved, and to attempt to quantify how many of each organism are potentially affected. Biomass measurements, numbers of eggs collected, and numbers and identification of larvae-to the level of major taxonomic groups, if possible shall be performed. Present "state-of-the-art" information shall be used to attempt to quantify the mortality of the organisms due to entrainment. This program shall determine the seasonal abundance of fish eggs and larvae.

Re ortin Re uirements Results. of this study shall be summarized in the Annual Environmental Report, If, at the end of two years, no significant problem is evident, an option to formally delete this portion of the Tech Specs may be initiated.

4.2 Im in ement of A uatic Organisms Ob'ective The purpose of this study is to assess the impingement of aquatic organisms on intake screens and the environmental impact of the impingement.

S ecification Intake screens washings shall be examined for a consecutive twenty-four hour period, twice a week whenever the Unit 1 circulating water pumps are operating. The collected washings shall be analyzed.

for the species present, number of each individual species caught, total biomass of each species, and the average size of the individuals caught.

Re ortin Regula,rements Data collected shall'be analyzed monthly for the first year of operation and a report sent to the NRC within 45 days of each monthly period. After the first year of operation, the data shall be analyzed every six months, and the results summarized in the Annual Environmental 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 minimum amount of chlorine necessary which will afford adequate protection to the condenser while avoiding unnecessaxy discharge of chlorine to the environment.

S ecification A program shall be initiated after Unit 1 has initially reached 75% power level. The initial chlorine injection rate shall be determined based on preoperational data, previous experience, and laboratory chlorine demand tests.

After reaching a power plateau above 75% power, a controlled incremental reduction of the chlorine injection rate- shall be implemented, Condenser fouling shall be monitored in coordination with chlorine reduction.

Re ortin Re uirements The results of this study Shall be summarized in the Annual Environmental Report. When the minimum level of chlorine usage, as determined by the study, has been reached, a proposal shall be submitted to the NRC to terminate the study, 4-2 Rev. 4 7/28/75

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 5.5.1 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 and provisions to ensure that plant systemswith components are operated in compliance the environmental technical specifications.

5.6 Re ortin Requirements

5. 6. 1 Routine Re orts 5.6.1.A. Annual Non-Radiolo ical Environmental 0 erato.n Re ort A'eport 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 as a separate document 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 and interpretations of the results of the non-radiological environ-mental surveillance activities (Section 3.0) and the environmental monitoring programs required by Limiting Conditions for. Operation.

This should also include 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 irreversible damage are detected by the monitoring, the licensee shall provide an. analysis of the problem and a proposed course of action to alleviate the problem.

5-5 Rev. 4 7/28/75

5.6.1.B. Annual'adi'o'lo i'cal Envi'ronmental 0 eratzn Re ort A report on the radiological environ-mental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental sur-veillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environ-ment. The reports shall also include the results of land use censuses required by the specif i cat ions. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.

Results of all radiological environmental samples taken shall be summarized on an annual basis. In the event that some results are not available within the 90-day period, the report shall be sub-mitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. ~

5.6.1.C Annual Radioactive Effluent Release Re ort A report on the radioactive discharges released from the site during the previous 12 months of operation. shall include the following:

Analyses of Effluent releases shall be sum-mariz'ed on a quarterly basis and reported in a format similar to Tables 5.6.1-A,B,C,GD.

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

5-6 Rev.4 7/28/75

Abnormal releases should be handled as batch releases for accounting purposes.-

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 wa te 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~ Spent resins, filter sludges, evaporator bottoms;

b. Dry compressible waste, con-taminated equipment, etc.;

c ~ Irradiated components, control rods, etc.;

d. 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 shipments. (Identify the number of shipments, 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 E E

2. Average release rate for period pCi/sec E E

3. Percent of Technical specification limit E E B. Zodines

1. Total iodine-131 Ci E E

2. Average release rate for period :pCi/sec E E

3. Percent of Technical specification limit E E C. Particulates

l. Particulates with half-lives 8 days E E

2. Average release rate for period pC1/sec E E

3. Percent of Technical specification limit E E

4. Gross alpha radioactivity E E D. Tritium

1. 'Ibtal release E E

2. Average release rate for period pCi/sec E 5-9 Rev.4 7/28/75.

TABLE 5.6.2-.C LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Qu-~r A. Fissionsand".activation products

l. Total release (not including tr~Mun, E E s, al ha)

2. Average diluted concentration yCi/ml E E during period

3. Percent of applicable limit E E B. Tritium concentration

1. Total release Ci E E

2. Average diluted pCz/ml E E dural iod

1. Total release Ci . E E

2. Average Chluted concentration durin riod pCi/ml E E

3. Percent of applicable limit E E D. Gross alpha radioactivity

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'iceEffl'uen't: 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 Those events requiring prompt reports shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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, telegr'aph, 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 Rev. 4 7/28/75

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;,2.b Radioactive Effluent Re orts Li uid Radioactive Wastes Re ort If the cummulative releases of radioactive materials in liquid effluents, excluding tritium and dissolved gases, should exceed one-half the design objective annual quantity during any calender quarter, the licensee shall make an investigation to identify the causes of such releases and define and initiate a program of action to reduce such releases to the design objective levels. A written report, of these actions shall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.

Gaseous Radioactive Wastes Re ort Should the conditions (a), (b), or (c) listed below exist, the licensee shall make an invest-igation to identify the causes of the release rates and define and initiate.a program of action to reduce the release rates to design objective levels. A written report of these actions shall be submitted to the NRC within 30 days from the end of the quarter during which the releases occurred.

(a) If the for average release rate the site during of noble gases any calendar quarter exceeds one-half the design objective annual quanity.

(b) If the average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter exceeds one-half the design objective annual quantity.

5-15 Rev. 4 7/28/75

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

Un lanned or Uncontrolled Release Re ort Any unplanned or uncontrolled offsite release of radioactive materials in excess of 0,5 Curie in liquid or in excess of 5 Curies of noble gases or 0,02 Curie of radioiodines in gaseous form requires notification. This notification must be made by a written report within 30 days to the NRC. The report shall describe the event, identify the causes of the unplanned or uncontrolled release and report actions taken to 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 radioactivity in an environmental medium exceeds ten times the control station value, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 10 days after confirmation of the validity of the measured level. Confirmation shall be completed at the earliest time consistent with wi'7g the analysis, but in any case,< 30 days. This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

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 proposed change.

5.7 Records Rentention 5.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant:

a. Records and drawings detailing plant design changes and modifications made to systems and equipment as described in 5.3,3,F.S.

5-16 Rev.4 7/28f75

b. Records of gll 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:

routine maintenance and component replacement, P.) equipment failures, (31 replacement of principal items of equipment ci Records of radioactivity levels in liquid and gaseous wastes released to the environment.

d. All reviews, including actions take and reasons therefore, required in Sections 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 Disorientation Australian pine or other suitable plants (i.e,,

native vegetation such as live oak, native figs, wild tamarind, and others) shall be planted, as a light screen, along the beach dune line bordering the. plant property to minimize turtle disorientation.

6-1 Rev. 4 7/28/75

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