ML17212B606

Proposed Radiological Effluent Tech Specs

ML17212B606
Person / Time
Site:	Saint Lucie
Issue date:	05/13/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17212B607	List: ML17212B606 ML17336A026
References
NUDOCS 8205200085
Download: ML17212B606 (68)

Text

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time inter-val from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performi.ng its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their, required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

PHYSICS TESTS 1.28 PHYSICS TESTS shall be those tests performed to measure the fundamen-tal nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the pro-visions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

UNRODDED INTEGRATED RADIAL PEAKING FACTOR F 1.29 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.

LOAD FOLLOW OPERATION 1.30 LOAD FOLLOW OPERATION shall be daily power level changes of more than 10% of RATED THERMAL POWER or daily insertion of CEAs below 'the Long Term Insertion Limit.

GASEOUS RADWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed tq reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system for decay.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.32 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoint methodology.

ST. LUCIE UNIT 1-6 8205200085 820513 PDR ADOCK 05000335 Nay 13, 1982 P .,- PDR

DEFINITIONS PROCESS CONTROL PROGRAM (PCP) 1.33 The PROCESS CONTROL PROGRAM shall be the procedures used by the licensee or his contractors, for the purpose of assuring that prior to shipment to a disposal facility, solidified radioactive waste (or waste containing free standing liquids) will be in a form (e.g., free standing liquids less than 1%) that meets the requirements for transportation and disposal pursuant to Title 10 of the Code of Federal Regulations and the applicable disposal site regulations.

SOLIDIFICATION 1.34 SOLIDIFICATION shall be the process which involves the addition of a solidifying matrix to radioactive waste for the purpose of binding or encapsulating (solidifying) such waste in a form (e.g., free standing liquids less than 1%) that meets the requirements for transportation and disposal pursuant to Title 10 of the Code of Federal Regulations and the applicable disposal site regulations.

DEWATERING 1.35 DEHATERING shall be the process of removing liquids from radioactive waste which contain free standing liquids, for the purpose of assuring that prior to disposal, such radioactive waste is in a form (e.g., free standing liquids less than 1%) that meets the requirements for transportation and disposal pursuant to Title 10 of the Code of Federal Regulations and the applicable disposal site regulations.

ST. LUCIE UNIT 1 1-6A May 13, 1982 I

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY At least once per 12 hours At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> At least once per 7 days 4/g* At least 4 per month and a minimum of 48 per year At least once per 31 days At least once per 92 days SA At least once per 6 months At least once per 18 months S/U Prior to each reactor start up Completed prior to each release N/A Not applicable

• For Radioactive Effluent Sampling

• • For Radioactive Batch Release only ST. LUCIE UNIT 1-8 May 13, 1982

INST RUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shall be operable as per Table 3.3-8.

APPLICABILITY: At all times ACTION aO With the number of OPERABLE meteorological monitoring channels required by Table 3.3-8, the Licensee should suspend all less'han releases of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel(s) is restored to OPERABLE status.'.

With less than the Minimum Channels OPERABLE as specified by Table 3.3-8, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4 One WIND SPEED, ONE WIND DIRECTION, and TWO AIR TEMPERATURE INSTRUMENTATION CHANNEL(S) shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

ST. LUCIE UNIT 'I 3/4 3-3O Hay 13, 1982

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT MINIMUM MINIMUM CHANNELS INSTRUMENT 6 ELEVATION ACCURACY OPERABLE

1. WINDSPEED

a. Nominal Elev (10 meters) + 0.5 *mph 1A

b. Nominal Elev (60 meters) + 0.5 *mph N.A.

2 ~ WIND DIRECTION 0 B

a. Nominal Elev (10 meters) + 5 1 0

b. Nominal Elev (60 meters) + 5 N.A.

3. AIR TEMPERATURE (Delta T) 0

a. Nominal Elev (10 meters) + 0,] C** 1'C 0

b. Nominal Elev (60 meters) 0~1 C** 1 0

c. Nominal Elev (35 meters) + 0.1 C** N.A.

• Starting speed of anemometer shall be ( 1 mph

• • Delta T measurement channels only A. The 60 meter Channel may be substituted for the 10 meter wind speed for up to 30 days in the event the 10 meter channel is INOPERABLE. Wind Speed Data from the 60 meter elevation should be adjusted using the wind speed power law:

S 10 meters = ( 60 meters) (0.1727)n where:

S = wind speed in mph n = 0.25 for Pasquill Vertical Stability Classes A, B, C, D.

n ~ 0.50 for Pasquill Vertical Stability Classes E, F, G.

1.727 X 10 = constant = 10 meters/ 60 meters B. The 60 meter Channel may be substituted for the 10 meter Wind Direction Channel for up to 30 days in the event the 10 meter Channel is INOPERABLE.

C. The 35 meter Channel may be substituted for one of the 10 meter or 60 meter Temperature Channels for up to 30 days if one of the Channels is INOPERABLE. The data -should always be normalized to C/100 meters to determine the vertical stability class.

ST. LUCIE UNIT 1 3/4 Nay 13, 1982

TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. WIND SPEED

a. Nominal Elev (10 meters) SA

b. Nominal Elev (60 meters) SA+

2. WIND DIRECTION

a. Nominal Elev (10 meters) D SA

b. Nominal Elev (60 meters) SA~

3. AIR TEMPERATURE (Delta T)

a. Nominal Elev (10 meters) SA

b. Nominal Elev (60 meters) SA

c. Nominal Elev (35 meters) SA~

• Required only if these Channels are being substituted for one of the Minimum Channels Operable as per Table 3.3-8.

INSTRUMENTATION RADIOACTIVE LIQU EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3 ."11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM methodology.

APPLICABILITY: As shown in Table 3 .3-12 .

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the number of channels required OPERABLE by Table 3.3-12, take the ACTION shown in Table 3.3-12.

c. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3 .9 Each radioactive liquid effluent monitoring instrumentation channel

'shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations during the Modes and at the frequencies shown in Table 4.3-8.

ST. LUCIE UNIT 1 3/4 3-45 Hay 13, 1982

ff TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Gross Radioactivity monitors, providing automatic termination of release

a. Liquid radwaste effluent line At all times* 18

b. Steam Generator blowdown effluent line At all times* 19

2. Gross Radioactivity Monitors not providing automatic termination of release

a. Component cooling water system At all times* 20

• During releases via this pathway

TABLE 3.3-12 TABLE NOTATION ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1 and;

2. At least two technically qualified members of the Facility Staff, one to perform, and one to verify the release rate calculations and discharge valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTON 19 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 90 days if there is no primary-to-secondary leakage indicated by the air ejector monitor. If the air ejector monitor indicates primary-to-secondary leakage, releases may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at limit of detection of at least 2 X 10-7 uCi/gm.

1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific, activity of the secondary coolant is )0.01 uCi/gram DOSE EQUIVALENT I-131.

2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is <0.01 uCi/gram DOSE EQUIVALENT I-131.

E ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection .of at least 2 X 10-7 uCi/ml.

ST. LUCIE UNIT 3/4 3-47 Hay 13, 1982

TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION FUNCTIONAL TEST

1. Gross Beta or Gamma Radioactivity Monitors providing alarm and automatic isolation

a. Liquid Radwaste Effluent Line P R(3) Q(1)

b. Steam Generator Blowdown Effluent Line R(3) Q(1)

2. Gross Beta or Gamma Radioactivity Monitors providing alarm but not providing automatic isolation (4)

a. Component Cooling Water Sys. R(3) Q(2)

• During releases via this pathway

TABLE 4.3-8 TABLE NOTATION (l) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs any of the following conditions exist:

if

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(3) The initial'HANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been calibrated against standards certified by the NBS. These standards should permit calibrating the system over its

~ intended range of energy and rate capabilities that are typical of normal plant operation. For subsequent CHANNEL CALIBRATION, button sources that have been related to the initial calibration may be used, at intervals of at least once per eighteen months. This can normally be accomplished during refueling outages.

(4) This requirement is applicable only to systems where the component cooling water system is discharged to an effluent stream.

ST. LUCIE UNIT 3/4 3-49 May 13, 1982

INSTRUMENTATION RADIOACTIVE GASEOUS PROCESS AND 'EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3 .11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM Methodology.

APPLICABILITY: As shown in Table 3 .3-13 .

ACTION

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.2.1 are met, declare the channel inoperable or reset the channel setpoints immediately to ensure that the limi.ts of 3.11.2.1 are met.

b. With less than the number of channels required OPERABLE by Table 3.3-13, take the ACTION shown in Table 3.3-13.

c. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.10 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-9.

ST. LUCIE UNIT 1 3/4 3-50 May 13, 1982

TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION A

MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor Radioactivity Rate 25 Measurement

2. Plant Vent, Fuel Bldg. Vent, ECCS-A Vent & ECCS-B Vent As per Table 3.3-6

3. Blowdown Building Vent System

a. Noble Gas Activity Monitor Radioactivity Rate 27 Measurement

b. Iodine Sampler Cartridge Verify presence of 30 cartridge

c. Particulate Sampler Filter Verify presence of -30 filter

4. Air Ejector Vent

a. Noble Gas Activity Monitor Radioactivity Rate 28 Measurement

5. Waste Gas Holdup System Explosive Gas Monitoring System (Gas Surge Tank)

a. Hydrogen (1)  % Hydrogen 29

b. Oxygen (1)  % Oxygen 29

• During releases via this pathway ontrol Tank

• • During Waste Gas System Operation when hydrogen is used as a cover gas on the Volume Contro a

TABLE 3.3-13 TABLE NOTATION ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tanks may be released to the environment for up to 30 days provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed, and

2. At least two technically qualified members of the Facility Staff, one to perform, and one to verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are collected and analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately route the Air Ejector Vent to the Plant Vent Pathway.

ACTION 29- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue indefinitely provided that grab samples are collected and analyzed at least once per shift.

ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may conti.nue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the end of sample collection.

ST. LUCIE UNIT 3/4 3-52 Hay 13, 1982

TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENZ MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL CHANNEL INSTRUMENT CHECK" CALIBRATION FUNCTIONAL TEST

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor R(3)

2. Plant Vent, Fuel Building Vent, ECCS-A Vent, 6 ECCS-B Vent As per Table 4.3-3

3. Blowdown Building Vent System

a. Noble Gas Activity Monitor R(3) Z(2)

b. Iodine Sampler N/A N/A

c. Particulate Sampler N/A N/A

4. Air Ejector Vent

a. Noble Gas Activity Monitor R(3) a(2)

5. Waste Gas Holdup System Explosive

-Gas Monitoring System

a. Hydrogen q(4)

b. Oxygen D** q(5)

• During releases via this pathway

• "During Waste Gas Holdup System Operation when hydrogen is used as a cover gas on the Volume Control Tank

~)

TABLE 4.3-9 TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs any of the following conditions exist:

if

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set. in operate mode.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been calibrated against standards certified by the NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities that are typical of normal plant operations. For subsequent CHANNEL CALIBRATION, button sources that have been related to the initial calibration may be used, at intervals of at least once per eighteen months. This can normally be accomplished during refueling outages.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. Nominal one volume percent hydrogen, balance nitrogen, and

2. Nominal four volume percent hydrogen, balance nitrogen.

(5) The GUNNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. Nominal one volume percent oxygen, balance nitrogen, and

2. Nominal four volume percent oxygen, balance nitrogen.

ST. LUCIE UNIT 1 3/4 3-54 May 13, 1982

3/4 ~ 11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site to unrestricted areas ( see Figure 3 .11-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. The concentration for total dissolved or entrained noble gases shall be limited to 2 X 10 4 uCi/ml.

APPLICABILITY: At all times ACTION a~ With the concentration of radioactive material released from the site to unrestricted areas exceeding, the above limits, immediately restore concentration within the above limits and provide prompt notification to the Commission pursuant to Specificatoin 6.9.1.12.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste to'e discharged shall be determined prior to release by sampling and analysis in accordance with Table 4 .11-1. The results of pre-release analyses shall be used with the calculational methods in the "ODCM" to assure that the concentration at the point of release is limited to the values in Specification 3.11.1.1.

4.11.1.1.2 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4 .11-1. The results of the analyses shall be used with the calculational methods in the "ODCM" to assure that the concentrations at the point of release are limited to the values in Specification 3.11.1.1.

4.11.1.1.3 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11-1.

ST. LUCIE UNIT 1 3/4 11-1 tray 13, 1982

TABLE F 11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type Of Detection (LLD)

Liquid Release Type Frequency Frequency Activity Analysis (uCi/ml) a A. Batch Waste Principal .Gamma Release Tanks Emitters 5 X 10 Each Batch Each Batch I-131 1 X 10 p Dissolved and One Batch/M Entrained Gases 1 X 10-5 H-3 1X105 Gross Alpha 1 X 10 Each Batch Composite Sr-89, Sr-90 SX108 Each Batch Composite Fe-55 1X10 B. Plant Continuous Principal Gamma Releases e, f Emitters 5 X 10 7 4/M 4/M I-131 1 X 10 Dissolved and 1 X 10 Entrained Gases H-3 1 X 10 5 4/M Gross Alpha 1X107 Composite 4/M Q Sr-89, Sr-90 SX108 Composite Fe-55 1 X 10 3/4 11-2 ST. LUCIE UNIT 1 May 13, 1982

TABLE 4 'l-l TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation- represents a "real" signal. The Lower Limit of Detection is a priori Limit where the analysis technique shall be capable of detecting the stated values if a blank sample were counted.

LLD= 4.66 S x 106 e-Lambda t Where:

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (in counts per minute) is the counting efficiency (as counts per transformation) is sample volume in appropriate units 6

2.22 X 10 transformations per minute per microCurie is the Chemical Separation Yield (when applicable) is base 2.71828 Lambda is decay constant is either:

The elapsed time between the midpoint of sample collection and the time of counting (for composite strontium only) 2 ~ The elapsed time between the sample time and the time at midcount (for pha counting only)

The units of t shall match the time units of Lambda in both cases.

b. A batch release is the discharge of liquid wastes of a discrete volume.

Each batch release tank shall be isolated and thoroughly mixed prior to sampling for a release.

c. The principal gamma emitters for which the LLD limit specification will apply are exclusively the following radionuclides: Mn-54, Pe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level.

ST. LUCIE UNIT I 3/4 11-3 May 13, 1982

TABLE 4.11-1 TABLE NOTATION

d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e. g., from a system that has an input flow during the continuous release.

f. If Component Cooling Water activity is >1 X 10 uCi/ml, perform a weekly gross activity on the Intake Cooling Water System outlet to ensure the activity level is ( a 2 X 10 uCi/ml LLD limit. If ICW is )2 X 10 7 uCi/ml, perform analysis in accordance with a Plant Continuous Release on this Table.

ST. LUCIE UNIT 1 3/4 11-4 May 13, 1982

Dcno tcs Unrestricted Ar~Boundry I,ine for. the ST. 'IE SITE

'I;<p;~kg'.:"', ~ ~,~".>~;"'gj~::;;@.~;, gFwj.:-".-:-

Minimum Distance for Radioactive Gaseous Releases from Plant Vent to Site Boundry j,J~pi>+~i~ .;~A:,;F

~

.W,,c~y i~We<<-~~>d!>,

Outlet to Discharge Pipe ( Liq. Radioactive Effluents Normal SCALE IN FEET 0 1000 2000 3000 I'~~<ere 3.$ l-l Uarestxicied Area Soumdry I'or Yhe St. Lucie Site Hay 13, 1982 11-5

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION II 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited:

During any calendar quarter to <1.5 mrem to the total body and to <5 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and subsequent quarters.

The Special Report exempts a Licensee Event R'eport on the above limits.

b. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 . Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with the methodology in the ODCM at least once per 31 days.

ST LUCIE UNIT 1 3/4 11-6 May 13, 1982

RADIOACTIVE EFFLUENT S LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The appropriate subsystems of the liquid radwaste treatment system shall be OPERABLE to reduce the radioactive materials in liquid waste prior to their discharge when the projected monthly dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days would exceed 0.12 mrem to the total body and 0.4 mrem to any organ.

APPLICABILITY: At all times ACTION'ith the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information (The Special Report exempts a Licensee Event Report on the above limits):

l. Identification of equipment or subsystems not OPERABLE and a description of alternate equipment used for treatment of radioactive liquid effluent.

2. Action(s) taken to restore the inoperable equipment, or backup equipment, to OPERABLE status.

J

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days as per the ODCM methodology unless the liquid radwaste treatment system is being used.

4.11.1.3.2 The appropriate liquid radwaste subsystems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate liquid radwaste subsystem has been utilized to process radioactive liquid effluents during the previous 92 days.

ST. LUCIE UNIT 1 3/4 11-7 May 13, 1982

RADIOACTIVE EFFLUENTS 3/4-11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The instantaneous dose rate in unrestricted areas (see Figure 3.11-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin, and

b. For the inhalation pathway the dose rate limit for I-131, Tritium and for radioactive materials in particulate form with half lives greater than 8 days shall be <1500 mrem/yr to any organ.

'V APPLICABILITY: At all times ACTION:

a~ With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the limit(s) given in Specification 3.11.2.1 and provide prompt notification to the Commission pursuant .to Specification 6.9.1.12.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The instantaneous release rate of noble gases in gaseous effluents shall be continuously monitored for the release points given in Table 3.3-13.

4.11.2.1.2 The release rate of radioactive materials other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.

4.11.2.1.3 The instantaneous dose rate in unrestricted areas, due to radioactive materials other than noble gases released in gaseous effluents, shall be determined to be within the required limits by using the methodology prescribed by the ODCM on the results of the sampling and analysis program specified in Table 4 .11-2 .

ST. LUCIE UNIT 1 3/4 11-8 May 13, 1982

TABLE 4 ~ 11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Lower Limit of Gaseous Release Type Frequency Analysis Type Of Detection (LLD)

Frequency Activit Analysis (UCi/101)

A. Waste Gas Storage Tank P P Noble Gas (Batch)g Each Tank Each Tank Principal Gamma Emitters 1X104 B. Containment Purge P P Noble Gas 1 X 10 Each Purge Each Purge Principal Gamma Emitters H-3 1X10 C. Plant Vent, Fuel Building Noble Gas 1X104 Vent, )lowdown Building Vent Principal Gamma Emitters System H-3 1X1O6 4/Mi 4/M H-3 1X 1O6 D. All Release Types as Listed I-131 1x 1o'2 in C. above Continuous . Charcoal Sample

.I-133 1 X 10 4 M Continuous Particulate Particulate Sample Principal Gamma Emitters 1X1O" M

Continuous Composite Gross Alpha 1X1O" Particulate Sample 0

Continuous Composite Sr-89; Sr-90 1X1O" Particulate Sample Continuous Noble Gas Monitor Noble Gas Gross Beta & Gamma 1 X 1O 4

TABLE 4.11-2 (continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.11-1.

b. The principal gamma emitters for which the LLD Limit Specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, Ce-144, and I-131 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

c. Tritium grab samples shall be taken prior .to each purge release, but the sample may be analyzed after the batch release when the sample counting solution has stabilized to allow an accurate determination of activity.

d. Sampling Frequency and Minimum Analysis Frequency are applicable only during releases via this pathway.

e. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Specifications 3 .11.2 .1, 3 .11.2 .2, and

3. 11.2.3.

f. If the analysis frequency is daily, the LLD limit may be increased by a factor of 10.

g. A batch release is the discharge of gaseous waste of a discrete volume.

h. A purge is a batch release from the containment building.

The Plant Vent shall be sampled for Tritium at this frequency Containment Purge Exhaust is operating as a continuous release.

if the ST. LUCIE UNIT 3/4 11-10 Nay 13, 1982

RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 3 .11-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to <5 mrad for gamma radiation and <10 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter. The Special Report exempts a Licensee Event Report on the above limits.

b. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations Cumulative dose contributions for the current calendar quarter shall be determined in accordance with the methodology in the ODCM at least once every 31 days.

ST. LUCIE UNIT '1 3/4 11-11 May 13, 1982

RADIOACTIVE EFFLUENTS DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gaes with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 3.11-1) shall be limited to the following:

a. During any calendar quarter to <7.5 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause( s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter. The Special Report exempts a Licensee Event Report on the above limit.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter shall be determined in accordance with the methodology in the ODCM at least once every 31 days.

ST. LUCIE UNIT 3/4 11-12 May 13, 1982

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The appropriate subsystems of the gaseous radwaste treatment system shall be OPERABLE. The gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to unrestricted areas (see Figure 3 .11-1) when averaged over 31 days would exceed 0.4 mrad for gamma radiation and 0.8 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a. With the gaseous Waste Treatment System inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information (The Special Report exempts a Licensee Event Report on the above limits):

1. Identification of equipment or subsystems not OPERABLE and a description of alternate equipment used for treatment of radioactive gaseous effluents.

2. Action(s) taken to restore the inoperable equipment, or backup equipment, to OPERABLE status.

3. Summary description of action( s) taken to prevent a recurrance.

b. The provisions of Specification 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be projected at least once per 31 days as per the ODCM methodology unless gaseous radwaste treatment system is in use.

4.11.2,.4.2 The appropriate 'subsystems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate subsystem has been utilized to process radioactive gaseous effluents during the previous 92 days.

ST. LUCIE UNIT '1 3/4 11-13 May 13, 1982

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3 ~ 11.2.5 The concentration of oxygen in the gaseous waste holdup system shall be limited to < 4% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times when hydrogen is used as a cover gas on the Volume Control Tank.

ACTION:

a. With the concentration of oxygen in the gaseous waste holdup system

)4% by volume, immediately suspend all additions of waste gases to the affected gas decay tank and reduce the concentration of oxygen in the remainder of the system to less than 4% by volume within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The affected gas decay tank should be discharged as soon as possible provided that the Specifications of 3.11.2.1 are not exceeded in the process.

b. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the gaseous waste holdup system shall be determined to be within the above limitsby monitoring the waste gases with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

ST. LUCIE UNIT 3/4 11-14

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to <285,000 Curies noble gases (considered as Xe-133).

APPLICABILITY: At all times ACTION:

a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1..12 'he written follow-up report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

b. The provisions of Specifications 3.0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Coolant System Gross Activity exceeds the activity limit of Specification 3.4.8.b.

ST. LUCIE UNIT 3/4 11-15 May 13, 1982

RADIOACTIVE EFFLUENTS

'OLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 Solidified radioactive waste or waste containing free standing liquids shall be processed in accordance with a PROCESS CONTROL PROGRAM prior to being shipped to a radioactive waste disposal facility.

APPLICABILITY: At all times ACTION

a. With the waste form requirements for transportation or disposal of solidified radioactive waste (or waste containing free standing liquids), pursuant to Title 10 of the Code of Federal Regulations and the applicable burial site regulations, not satisfied, suspend shipments of such radioactive waste to the burial site.

b. The provisions of Specifications 3.0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 For each radioactive waste container used to collect liquid radioactive waste (or waste containing free standing liquids), prior to shipment to a radioactive waste disposal facility, the licensee shall certify that he has followed the minimum requirements of the applicable procedures of the PROCESS CONTROL PROGRAM.

ST. LUCIE UNIT ] 3/4 11-16 May 13, 1982

3/4. 12 RADIOLOGIC ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiologica environmental monitoring program shall e conducte as specified in Table 3.12-1 and Table 4.12-1.

APPLICABILITY: At all times.

ACTION a~ With the radiological environmental monitoring program not being conducted as specified in Tables 3.12-1 and 4.12-1, prepare and submit to the Commission, in the annual Radiological Monitoring Report, a description of the reasons for not conducting the program as specified. Deviations from Specification 3 .12.1 may occur because samples are unobtainable due to hazardous conditions, biological or seasonal unavailability, or due to vandalism, or to malfunction of sampling or analytical equipment, laboratory accidents, sampling errors, or other legitimate reasons. If deviations occur because of malfunction of sampling or analytical equipment, every effort shall be made to complete corrective action prior to the end of the next sampling period. A description of all deviations from Tables 3.12-1 and 4.12-1, the reasons for all such deviations and a description of any corrective actions initiated or planned to bring the radiological environmental surveillance program back in accordance with Specification 3.12.1 shall be provided in the annual Radiological Environmental Monitoring Report. A current list of sample locations used during the reporting period shall be included in the annual Radiological Monitoring Report. Sample location changes from the year, if any, should be identified along with a brief 'receding description of the reason for the change.

b. With the confirmed* level of radioactivity in an environmental sampling medium at one or more of the locations, outside of the plant circulating water system, specified in Table 3.12-1 exceeding the limits of Table 6.9.3-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter (or from the time of the confirmatory result if such result is not received until after the end of the quarter in which the original sample was collected), a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which may have caused the limits of Table 6.9.3-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the conditions shall be reported and described in the annual Radiological Environmental Monitoring Report. This Special Report exempts a Licensee Event Report.

• A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be completed at the. earliest time consistent with the analysis, but in any case within 30 days.

ST. LUCIE UNIT 'I 3/4 12-1 May 13, 1982

c. With milk or garden vegetation samples unava lable from any of the sample locations required by Table 3.12-1, information shall be included in the annual Radiological Monitoring Report identifying the cause of the unavailability and identifying replacement locations where samples were obtained. If replacement samples are unavailable during the specified time interval, a special report pursuant to specification 6.9.2 shall be submitted to the Commission within 30 days from the time the licensee has been properly notified and will identify the cause of the unavailability of the samples and a discussion of the plans for obtianing future samples. If new permanent sample locations are required; once they have been selected and sample availability is established, the locations from which the samples are unavailable may be deleted from the program, and the locations from which the samples will be obtained in the future are incorporated in the environmental monitoring program as new sample locations.

SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.

ST. LUCIE UNIT 1 3/4 12-2 Hay 13, 1982

iL ~

TABLE 3.12-1 ST. LUCIE SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fxposure Pathway Sample Sampling and (b) Type and Frequency (c) and/or Sample Locations Collection Frequency of Analysis

l. Airborne

a. Radioiodine & 9 locations Continuous operation of Radioiodine filters Particulates sampler with collection I-131 weekly at least weekly Particulate filters Gross beta weekly: Analyze each filter for gross beta radioactivity > 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Gamma isotopic (Composite)

Quarterly A gamma isotopic is also required for each sample having a gross beta radioactivity which is >1.0 pCilm3and which is also >10 times that of the most recent control sample.

2. Direct Radiation 29 locations Quarterly Gamma exposure'ate quarterly

3. Waterborne

a. Surface 4 locations Monthly Gamma isotopic and tritium analysis Monthly

b. Ground (well) 2 locations Quarterly Gamma isotopic and tritium analysis Quarterly

c. Drinking 3 locations Quarterly Gross beta, gamma isotopic and tritium analysis Quarterly

d. Sediment from 4 locations Semiannually Gamma isotopic analysis shoreline Semiannually

TABLE 3 ~ 12-1 ST. LUCIE SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and b) Type and Frequency (c and/or Sample Locations Collection Fre uency of Analysis

4. Ingestion

a. Milk 2 locations Semi-Monthly Gamma isotopic and I-131 analysis Control samples Monthly Semi-monthly.-

Control samples Gamma isotopic and I-131 analysis Monthly

b. Fish and Invertebrates

1. Crustacea 2 locations Semi-Annually Gamma isotopic analysis Semi-Annually

2. Fish 2 locations Semi-Annually Gamma isotopic analysis Semi-Annually

c. Food Products

1. Citrus 5 locations At harvest time Gamma isotopic analysis Each Sampling

2. Edible Garden Vegetation 2 locations At harvest time Gamma isotopic analysis Each Sampl

TABLE 3.12-1 TABLE NOTATION (a) A list of sample locations will be provided on a Figure and Table in the ODCM.

(b) The following definition of frequencies shall apply to Table 3.12-1 only:

Weekly Not less than once per calendar week. A maximum interval of 11 days is allowed between the collection of any two consecutive samples.

Semi-Monthly Not less than 2 times per calendar month with an interval of not less than 7 days between, sample collections. A maximum interval of 24 days is allowed between collection of any two consecutive samples.

Monthly '- Not less than once per calendar month with an interval of not less than 10 days between sample collections.

Quarterly Not less than once per calendar quarter with an interval of not less than 30 days between sample collections.

Semiannually One sample each between calendar, dates (January 1 - June will be provided between sample collections.

(c) Frequency of analyses to be consistent with collection frequency.

(d) No drinking water sources are effected by effluents from the plant.

ST. LUCIE UNIT 3/4 12-5 May 13, 1982

TABLE 4.12-1.

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

ANALYSIS WATER AIRBORNE PARTI- FISH MILK FOOD PRODUCTS SEDIMENT (PCI/L) CULATE 0( GAS (pCi/Kg, wet) pCi/L (pCi/Kg, wet) (pCi/Kg, dry)

(pCi/m )

Gross Beta 4c 1 X 10 H-3 2000 (1000 )

~ Mn-54 15 130

~ Fe-59 30 260 Co-58, 60 15 130

' ~ Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1c 1X1O' 6Od Cs-134 15 X 10 130 150 6O'Od Cs-137 18 6X1O2 150 18 180 Ba/La-140 35 35 Note: This list does not mean that only these radionuclides are to be detected and reported.

Other peaks which are raeasurable and identifiable (except naturally occurring radionuclides) together with the above radionuclides shall also be identified and reported.

TABLE 4.12-1 (continued)

NOTATION

a. Acceptable detection capabilities for thermoluminescent dosimeters used, for environmental measurements are given in Regulatory Guide 4.13.

b. Table indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration, of radioactive material in a sample that will yield a net count (above system background) that will be detected with at least 95% probability with at most 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4 66* sb LLD = E V'22 Y where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume).

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per disintegration).

V is the sample size (in units of mass or volume).

2.22 is the number of disintegrations per minute per picocurie.

Y is the fractional radiochemical yield (when applicable).

• 4.66 is the factor used when background has. been subtracted from the sample count. For measurements in which the background is not subtracted, the factor 3 .29 shall be used.

c LLD for drinking water d LLD for garden vegetation e Total for parent and daughter ST. LUCIE UNIT 1 3/4 May 13, 1982

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted annually to identify the location of the nearest milk animal, the nearest residence and the nearest garden+ of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times ACTION:

a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values ccurrently being calculated in Specification 4.11.2.3, prepare and submit to the Commission within 60 days from the time the licensee receives the results of the Land Use Census, pursuant to Specification 6.9.2, a Special Report, which identifies the new location(s).

b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20%

greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission within 60 days from the time the licensee receives the results of the Land Use Census, pursuant to Specification 6.9.2, a Special Report, which identifies the new location(s). The new location shall be added to the radiological environmental monitoring program when samples become available. The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from the monitoring program after (October 31) of the year in which the land use census was conducted.

c. The provisions of Specifications 3 .0.3 and 3 .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of February 1 and July 31, by door-to-door survey, aerial survey, or by consulting local agriculture authorities.

• Broad leaf vegetation sampling may be performed at the site boundary in a sector with the highest D/Q in lieu of the garden census.

ST. LUCIE UNIT ). 3/4 12-8 May 13, 1982

iO I

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 ~ 12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION

• 3.12.3 Analyses shall 'be performed on radioactive materials supplied as part of an.Interlaboratory Comparison Program which has been approved by NRC. This condition may be satisfied by participation in the Environmental Intercomparison Studies Program conducted by the EPA.

APPLICABILITY: At all times.

ACTION:

I

a. With analyses not being performed as required above, notify the Commission as a part of the annual Radiological Environmental Monitoring Report.

b. The provisions of Specification 3 .0.3 and 3 .0.4 are not applicable.

If the Radiologi'cal Environmental Surveillance Program is carried out by the licensee, the licensee shall establish an Interlaboratory Comparison Program which'as been approved by the NRC. If the licensee is not the principle investigator, the licensee shall require the principle investigator to take part in an Interlaboratory Comparison Program. This condition may be satisfied by participation in the Environmental Radioactivity Laboratory Intercomparison Studies Program.

SURVEILLANCE REQUIREMENTS 4.12.3 The results of available analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the annual Radiological Environmental Monitoring Report pursuant to Specification 6.9.3.2.

ST. LUCIE UNIT f 3/4 12-9 Hay 13, 1982

INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm trip setpoints for these instruments shall be calculated in accordance with approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

ST. LUCIE UNIT 1 B 3/4 3-4 May 13, 1982

3/4 ~ 11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1 ' CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2 .

3/4 '1 '.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable".

Performing the dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents should be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dis'persion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

ST ~ LUCIE UNIT 1 B 3/4 11-1 May 13, 1982

RADIOACTIVE EFFLUENTS BASES This specification- applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4 ~ 11 ~ 1.3 LIQUID WASTE TREATMENT The OPERABILITY of appropriate subsystems of the LWT" system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section 11.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/F 11.2 ' DOSE RATE This specification is provided to ensure that the dose rate at anytime at the exclusion area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table 11. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate fo'r any increase in the atmospheric diffusion factor above that for the exclusion area boundary.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to <(500) mrem/year to the total body or to <(3000) mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding organ dose rate above background to an infant via the inhalation pathway to < 1500 mrem/year.

J ST. LUCIE UNIT 1 B 3/4 11-2 May 13, 1982

RADIOACTIVE EFFLUENTS BASES 3/4 11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable" . The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents should be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. The ODCM Equations provided for determi,ning the air doses at the exclusion area boundary will be based upon the historical (or real) average atmospheric conditions.

3/4 .11.2 .3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for, the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from ST. LUCIE UNIT 1 B 3/4 11-3 Hay 13, 1982

RADIOACTIVE EFFLUENTS BASES Light-Mater-Cooled Reactors", Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical (or real) average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) depositon on the ground with subsequent exposure of man.

3/4-11.2.4 GASEOUS WASTE TREATMENT The OPERABILITY of the appropriate subsystems of the gaseous radwaste treatment system ensures that the system will be available for use whenever gaseous effluents require holdup prior to release to the environment. The requirement that the appropriate portions of these systems be used when speci, fied provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of'10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections 11B and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

ST. LUCIE UNIT 1 B 3/4 11-4 May 13, 1982

RADIOACTIVE EFFLUENTS BASES 3/F 11.2 ' EXPLOSIVE GAS MIXTURE This'pecification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10CFR Part 50.

3/F 11.2.6 GAS DECAY TANKS Restricting the quantity of radioactivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tanks conten6s, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem, as per Safety Guide 24. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure".

ST. LUCIE UNIT I B 3/4 11-5 Hay 13, 1982

s 3/4. 12 RADIOLOG AL ENVIRONMENTAL MONITORING BASES t

The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Program changes may be initiated based on operational experience.

The detection capabilities required by Table 4 .12 .-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD limits for drinking water meet the requirements of 40 CFR 141.

3/4 ~ 12 ~ 1 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and,that modifications to the monitoring program are made if required by'he results of this census. This census satisfies the requirements of Section IV.8.3 of Appendix I to 10 CFR Part

50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this mimimum garden size, the following assumptions were used, 1) that 20X of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter. Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest (D/Q) in lieu of performing the garden census.

3/4 '2.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance'rogram for environmental monitoring in order to demonstrate that the results are reasonably valid.

ST. LUCIE UNIT '1 B 3/4 12-1 May 13, 1982

ADMINISTRATIVE ROLS

e. Investigation of all violations of the Technical Specifications including the preparation and, forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Energy, the Vice President of Nuclear Energy and to the Chairman of the Company Nuclear Review Board.

f. Review of those REPORTABLE OCCURRENCES requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

g. Review of facility operations to detect potential safety hazards.

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

i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

k. Review the results of the radiological environmental monitoring program at least once per 12 months.

1. Review of the ODCM and any changes to the ODCM.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a.'ecommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President of Nuclear Energy and the Company Nuclear Review Board of disagreement the FRG and the Plant Manager; however, the Plant Manager 'etween shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

ST. LUCIE UNIT 1 6-7 Hay 13, 1982

ADMINISTRATIVE ROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall'e taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission, the Vice President of Power Resources and to the CNRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the FRG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the CNRB and the Vice President of Nuclear Energy within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities'eferenced below:

a~ The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33,,November, 1972.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

go PROCESS CONTROL PROGRAM for SOLIDIFIED radioactive waste or waste containing free standing liquid.

h. Offsite releases of gaseous and liquid effluents containing radioactive materials, including effluent monitor setpoints.

i. Offsite Dose Calculation Manual ST. LUCIE UNIT 1 6-13 May 13, 1982

ADMINISTRATIVE ROLS d.Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Delta k/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Delta k/k; or occurrence of any unplanned criticality.

e.Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the FSAR.

f.personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the FSAR.

g.Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.

h.Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

i.Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

jexcess

.Occurrence of radioactive material contained gas decay tanks in of that permitted by the limiting condition for operation established in the technical specifications.

k.Exceeding L.C.O. 3 ~ 11 ~ 1 1 (Liquid Radwaste Concentration) or

~

L.C.O. 3.11.2.1 (Gaseous Dose Rate).

ST LUCIE UNIT 6-17 Hay 13, 1982

ADMINISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances suxrounding the event.

a. Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

c. Observed inadequacies in the implementation of administrative or procedural controls whi'ch threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature'ystems.

d. Abnormal degradation of systems other than those specified in 6.9.1.12 .c above designed to contain radioactive material resulting from the fission process.

e. An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:

1.A descxiption of the event and equipment involved.

2.Cause(s) for the unplanned xelease.

3.Actions taken to prevent recurrence.

4.Consequences of the unplanned release.

ST. LUCIE UNIT '1 6-18 Hay 13, 1982

ADMINISTRATIVE CONTROLS SPECIAL REPORTS

h. Core Barrel Movement, Specifications 3 .4.11 and 4 .4.11.

i. Fire Detection Instrumentation, Specification 3 .3.3.7.

Fire Suppression Systems, Specification 3 .7.11.1.

k. Exceeding one or more LCO' for Specifications 3 .11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, or 3.11.2.4, involving radiation dose from radioactive effluents.

1. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9.3-2 when averaged over any calendar quarter sampling period pursuant to Specification 3.12.1.b. When more than one of the radionuclides in Table 6.9.3-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ...>1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 6.9.3-2 are detected and are the result of plant effluents, this report shall be submitted the quarterly dose to an individual is equal to or greater than the if quarterly limits of Specifications 3 .11 .1 .2, 3 .11.2 .2 and 3.11 .2.3 .

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

m. Milk or garden samples unavailable during the specified time interval, Specification 3.12.l.c.

,n. The discovery of a location which yields a calculated dose or dose commitment > the values currently being calculated, Specification 3.12;2.a.

o. The discovery of a location which yields a calculated dose or dose commitment 20% greater than at a location from which samples are currently being obtained, Specification 3.12.2.b.

ST. LUCIE UNIT 'I 6-19 Nay 13, 1982

ADMINISTRATIVE CONTROLS 6.9.3 ENVIRONMENTAL REPORTS RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 3/

6.9.3.1 Routine radiological environmental monitoring reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

6.9.3.2 The annual radiological environmental monitoring reports shall include summaries, interpretations, and information based upon trend analysis of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls t,as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment., The reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the 'problem.

The annual radiological environmental monitoring reports shall include summarized and tabulated results in the format similar to Table 6.9.3-1 of all radiological environmental samples required to be taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. Delayed data shall be submitted in a supplementary report within 60 days from the time the last analyses are completed.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the result of land use censuses required by the Specification 3.12.2; a summary of available results from the Interlaboratory Comparison Program required by Specification 3.12.3, and additional information as provided in Specification 3 .12.1.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3/

6.9.3.3 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

3/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

ST. LUCIE UNIT 1 6-20 Hay 13, 1982

TABLE 6.9.3-1 FORHAT FOR ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMHARY NAME OF FACILITY DOCKET NO.

LOCATION OF FACILITY REPORTING PERIOD Type and Lower Limit All Indicator Location With Highest Annual Mean Number of Medium or Pathway Total Number of Locations Control Locations Nonroutini Sampled of Analyses Detection Mean (f)a Name Mean( f) a Mean (f)a ~

Reported (Unit of Measurement) Performed (LLD) Rangea Distance and Direction Ra e Range Measurements Mean and range based upon detection measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis (f).

ADMINISTRATIVE CONTROLS 6.9.3.3.1 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 Rev; 1, "iMeasuring, Evaluating, and Reporting Radioactivity. in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Mater-Cooled Nuclear Power Plants", with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned release.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in the ODCM. The assessment of radiation doses shall be performed in accordance with methodology in the ODCM.

ST. LUCIE UNIT f 6-22 Hay 13, 1982

TABLE 6.9.3-2 NONROUTINE REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Broad Leaf Water Airborne Particulate Fish Milk Vegetation Analysis (pCi/1) or Gases (pCi/m ) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet)

I H-3 2 X 104 Mn-54 1 X 103 3 X 104 Fe-59 4 X 102 1 X 104 I Co-58 1 X 103 3 X 104 I Co-60 3 X 10 1 X 10 I Zn-65 3X10 2 X 104

'Zr-Nb-95 4 X102 I-131 0.9 1 X 102 I Cs-134 30 10 1 X 10 60 1 X 103 I Cs-137 50 20 2X10 70 2 X 103 (1)

I

. Ba-La-140 2 X 102 3 X102 (1) Total for parent and daughter

< h ADMINISTRATIVE CONTROLS

e. Records of gaseous and liquid radioactive material released to the environs

f. Records of transient or operational cycles for those facility components identified in Table 5.9-1.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

Records of Quality Assurance activities required by the QA Manual Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59

k. Records of meetings of the FRG and the CNRB

1. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

m. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-2a and 3 .7-2b including the date at which the service life commences and associated installation and maintenance records.

n. Annual Radiological Environmental Monitoring Reports; and records of analyses transmitted to the licensee which are used to prepare the Annual Radiological Environmental Monitoring Report.

o. Meteorological data, summarized and reported in a format consistent with the recommendations of Regulatory Guides 1.21 and 1.23 .

6.11 RADIATION PROTECTION PROGRAM Procedures'or personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

ST. LUCIE UNIT I 6-24 May 13, 1982

ADNINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12 1 In lieu of the "control device" or "alarm signal" required by

~

paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgable of them.

c. An, individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist.

• Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

ST. LUCIE UNIT 1 6-25 May 13, 1982

ADMINISTRATIVE CONTROLS 6.17 PROCESS CONTROL PROGRAM (PCP) 6.17.1 The licensee's PCP for SOLIDIFICATION (if applicable) shall be approved by the Commission prior to implementation; or 6.17.2 If the licensee uses a contractor to solidify radioactive wastes, the licensee shall use a contractor (or contractor'-s PCP"for SOLIDIFICATION) which has been approved by the Commission.

6.17.3 Licensee initiated change(s) to his PCP for SOLIDIFICATION:

1. Shall become effective upon review and acceptance by the FRG

2. Shall be'ubmitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s) was made. The information submitted shall contain:

a.A description of the change(s) which was made and the reasons for such changes.

b.A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.Documentation of the fact that the change has been reviewed and found acceptable by the FRG.

6.17.4 Licensee initiated changes to the PCP for DEWATERING:

1. Shall become effective upon review and acceptance by the FRG.

6.18 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.18.1 The ODCM shall be approved by the Commission prior to implementation 6.18.2 Licensee initiated changes to the ODCM:

1. Shall be 'aproved by the Facility Review Group (FRG) and shall become effective upon FRG approval.

2. Shall be reported to the NRC as an attachment to the Semiannual Radioactive Effluent Release Report for the reporting period that the change(s) were implemented. This attached report shall contain:

a.A FRG approved copy of the ODCM showing the changes b.A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.

ST. LUCIE UNIT I 6-2 7 tray 13, 1982

pe 0

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