ML20071J740

Draft Radiological Effluent Tech Specs

ML20071J740
Person / Time
Site:	Calvert Cliffs
Issue date:	04/23/1982
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20071J736	List: ML20071J733 ML20071J740
References
NUDOCS 8204270358
Download: ML20071J740 (24)

Text

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1 CALVERT CLIFFS NUCLEAR POWER PLANT DRAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS l

i 82,04270358

l.0 DEFINITIONS (Continued)

GASEOUS RADWASTE TREATMENT SYSTEM 1.29 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gasses from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.30 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

PURGE - PURGING 1.31 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

VENTING 1.32 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a j VENTING process.

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING 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 in accordance with approved plant procedures.

APPLICABILITY: WHEN DISCHARGING TO THE ENVIRONMENT ACTION:

A. With a radioactive liquid effluent monitoring instrumentation inoperable, suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

B. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, taken 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 montoring instrumentation channel shall be demonstrated OPERABLE as described by approved plant procedures.

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TABLE 3.3-12 RADIOACTIVE LtOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM I INSTRUMENT CHANNELS OPERABLE ACTION l

1. GROSS RADIOACTIVITY MONITORS i PROVIDING AUTOMATIC TERMINA- '

TION OF RELEASE

a. Liquid Radwaste Effluent Line (1) 28

b. Steam Generator Blowdown (1) 29 TABLE NOTATION ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release, at least two independent samples are analyzed in accordance with Specification 4.11.1.1.2 and the release rate calculations verify compliance with Specification 3.11.1.2.

ACTION 2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least IE-7 microcuries/ gram:

a. 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 greater than 0.01 microcuries/ gram DOSE EQUIVALENT l-131.

b. 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 less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT l-131.

ACTION 3 With the number of channels OPERABLE less than required by the Minirrum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least IE6 gpm dilution water is available.

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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set in accordance with approved plant procedures.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation inoperable, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, 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 REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE in accordance with approved plant procedures.

TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABLITY ACTION

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Release (1) ** 35

2. U-l VENT HEADER SYSTEM

a. Noble Gas Activity Monitor (1)

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b. lodine Sampler (1) 37

c. Particulate Sampler

• 37 (1)

d. Flow Rate Indicator

• 36 (1)

3. U-2 VENT HEADER SYSTEM

a. Noble Gas Activity Monitor (1)

• 37

b. Iodine Sampler

• 37 (1)

Particulate Sampler *

c. (1) 37

d. Flow Rate Indicator

• 36 (1)

At all times

• • During releases to the environment TABLE NOTATION ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release at least two independent samples of the tank's contents are analyzed, the release rate calculations are verified and the applicable vent header system is operable.

ACTION 36 With the number of channels OPERABLE, less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is assumed to be at its maximum rated capacity.

ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue for up to 30 days provided grab samples are taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling.

e 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLIJENTS CONCENTR A TION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other l

than dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits, as soon as practical.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.

4.11.1.1.2 The concentration of radioactive liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1.

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TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM TYPE OF OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS ACTIVITY ANALYSIS (LLD)

(uCi/ml)"

P P

a. Batch Waste Each Batch Each Batch Principal Gamma 5E-7 Release Emittersf d

Tanks l

l P M l Each Batch Composite b H-3 IE-5 l Gross Alpha IE-7 P Q Each Batch Composite b Sr-89,Sr-90 SE-8

b. Continuous Grab Sample W Principal Gapma Releases Composite c Emitters SE-7 M

Grab Sample Composite c H-3 lE-5 Gross Alpha IE-7 Q

Grab Sample Compositec Sr-89, Sr-90 SE-8

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a. The LLD is the smallest concentration of radioacive material in a sample that will be detected with 95% probability with 5% probability of fasely concluding that a blank observatica represents a "real" signal as defined in the HASL-300 manual.

b. 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 liquid released.

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in proportion to the volume of the effluent stream. Prior to analyses, j all samples taken for the composite shall be thoroufnly mixed in order for the composite sample to be representative of tr e ef fluent release.

d. A batch release is the discharge of liquid waste of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated.

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

f. Cesium-137 will be considered as the representative gamma emitter for achieving the LLD requirements.

R ADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited to:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 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, in lieu of any other report required by Specification 6.9.1, prepare and submit to l 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 describes ongoing and planned corrective actions which are intended to reduce the releases of radioactive materials in liquid effluents during the remainder of the calendar year, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to total body and 10 mrem to any organ.

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

SURVElLLANCE REOUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined for each month, by calculational methods delineated in approved plant procedures

RADIOACTIVE EFFLUENTS LIOUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 A liquid radwaste treatment system as described in plant procedures shall be OPERABLE. The appropriate portions of the treatment system described in the plant procedures shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the dose commitment exceeds 0.7) mrem to the total body and 2.5 mrem to any organ in a calendar quarter.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability.

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

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.

SilRVEILLANCE REQUIREMENTS 4.11.1.3 Cumulative quantities of liquid releases shall be determined for each month by calculational methods delineated in approved plant procedures.

l RADIOACTIVE EFFLIJENTS 3/4.11.2 GASEOUS EFFLtJENTS l DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin, and

b. For all radiciodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than 8 days: Less than or equal to 1500 mrem / year to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the above limits, decrease the release rate to within the above limit (s) as soon as practical.

513RVEILLANCE REOIJIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with plant procedures.

l 4.11.2.1.2 The dose rate due to radioactive materials, other than noble gases, in gaseous ef fluents shall be determined to be within the above limits in accordance with plant procedures by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

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TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF ACTIVITY GASEOUS RELEASE SAMPLING ANALYSIS ANALYSIS LLD(uCi/ml)a TYPE FREQUENCY FREQUENCY Batch Release Each Batch Each Batch Principal Gagma IE-4 Emitters H-3 IE-6 Continuous Charcoal b l-131 IE-12 Releases e Once Per Continuous 7 Days 2

Continuous Particulate b Principal Gamma IE-11 Once Per 7 Days Emittersd Particulate b e Monthly Continuous Gross Alpha IE-11 Composite c

Continuous Particulate Quarterly Sr-89, IE-Il Composite Sr-90 e

Continuous Monthly H-3 IE-6 b

Grab Weekly Principal Gamma IE-6 Emittersd

l TABLE 4.11-2 (CONTINUED)

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, as defined in the HASL-300 manual.

b. Analyses shall also be performed whenever the noble gas monitor indicate a significant change in the isotopic mixture as indicated by the noble gas monitor of the effluent discharge line. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.

c. Samples shall be taken continuously except for those periods in which the samples are replaced.

d. Cesium-137 will be considered as the representative gamma emitter for achieving the LLD requirements.

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l R ADIOACTIVE EFFLUENTS l DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the 1

following: I

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculation air dose for radioactive noble gas in gaseous ef fluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar year, so that the cumulative dose is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b. The provisions of Specificativ i.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE REQUIREMENTS l

I 4.11.22 Dose Calculations cumulative dose contributions for the current calendar quarter and current calendar year shall be determined for each month by calculational methods delineated in approved plant procedures.

e RADIOACTIVE EFFLUENTS 1

DOSE - R ADIOIODINES, R ADIOACTIVE MATERIALS IN PARTICULATE FOP.M, AN?, l RADIONUCLIDES OTHER THAN NOBLE GASES l 1

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines and radioactive materials in particulate form, and radionuclides (other than noble gases), with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ.

b. During any calendar year. Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radiciodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, 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 describes ongoing and planned corrective actions which are intended to reduce the releases of radiciodines and radioactive materials in particulate form, and radionuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar year, so that the cumulative dose or dose commitment to an individual from these releases in is within 15 mrem to any organ.

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

StJRVEILLANCE REOlllREMENTS 4.11.2.3 Dose Calculations cumulative dose contributions for the current calendar quarter and current calendar year shall be determined for each month by calculational methods delineated in approved plant procedures.

1 R ADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTM and VENTILATION EXHAUST SYSTEM as described in plant procedures shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the dose commitment due to gaseous i effluent releases from the site exceeds,2.5 mrad for gamma radiation,5 mrad for beta radiation, or 3.7 mrem to any organ.

APPLICABILITY: At all times ACTION: j j

a. With gaseous waste being discharged without treatment except for periods of maintenance and in excess of the above limits, in lieu of j any other repart required by the Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability.

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

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.

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l SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be calculated for each month by calculational methods delineated in approved plant procedures.

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1 RADIOACTIVE EFFLUENTS l

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 less than or equal to 58,500 curies noble gases (considered as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limits, 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 /> reduce the tank contents to within the 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 storage tank shall be sampled and determined at least weekly when radioactive materials are being added to the tank.

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l R ADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.3 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid gaseous effluents exceeding twice the limits of Specification 3. I 1.1.a, 3. I 1.1.a.b, 3. I 1.2.2.a., 3. I 1.2.2.b, 3. I 1.2.3.a,

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or 3.ll.2.3.b, in lieu of any other report required by Specification 6.9.1, prepare and submit a special report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, i Washington, D.C. 20555, within 30 days, which defines the  !

corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to an member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that inc' odes the release (s) covered by this report.

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

SURVEILLANCE REQUIREMENTS 4.11.4 Cumulative dose contributions from liquid and gaseous effluents shall be determined for each month by calculational methods delineated in  !

approved plant procedures.

3.4.11.1 RADIOACTIVE EFFLLIJENTS BASES 3/4.11.1 LIO1110 EFFLtJENTS 3/4 11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B., Table 11, Column 2. This limitation provides additinal l

assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section ll.A. design objectives of Appendix I,10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population.

3.4.11.1.2 DOSE This specification is provided to implement the requirements of Sections ll.A., Ill.A., and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A.

of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A. of Appendix 1 to assure that the releases of radioactive material in liquid ef fluents will be kept "as low as is reasonably achievable."

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3.4.11.1 RADIOACTIVE EFFLUENTS BASES 3.4.11.1.3 LIOUID WASTE TREATMENT l The requirement that the appropriate portions of this system be used l

when specified provides assurance that the releases of radioactive

materials in liquid effluents will be kept "as low as is reasonable achievable". This specification is one of the measures which implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of

Appendix A to CFR Part 50 and their design objective given in Section 11.0 of Appendix I to 10 CFR Part 50.

3.4.11.2 GASEOUS EFFLUENTS

! 3.4.11.2.1 DOSE RATE This specification is provided to ensure that the releases of gaseous effluents from all units on the site will result in doses which are within  ;

the annual dose limits of 10 CFR Part 20 for unrestricted areas. The l annual dose limits are the doses associated with the concentrations of 10 CFR Part 10, Appendix B, Table II, Column 1. Limits on hourly average release rates (noble gases) and weekly release rates for materials in specification 3.11.2.1 will 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 site i 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)).

RADIOACTIVE EFFLIJENTS 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 Conditon for Operation implements the guides set forth in Section II.B.

of Appendix 1 and assures that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

3.4.11.2.3 DOSE - RADIOIODINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, !!!.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section ll.C of Appendix 1. assures releaes of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

3.4.11.2.4 GASEOtJS RADWASTE TREATMENT The requirement that the appropriate portions of these systems be used, l when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is

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reasonable 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 the Design Objectives given in Section 11.0 of Appendix I to 10 CFR Part 50.

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I BASES 3.4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of a uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.

3.4.11.3 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 l CFR 190 until NRC staff action is completed. An individual is not -

I considered a member of the pubic during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel j cycle.

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ADMINISTRATIVE CONTROLS SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTN 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted witin 60 days af ter January 1 and July I of each year.

6.9.1.9 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, " Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releses of Radioactive Materials in Liquid and Gaseous Ef fluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 197te, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report to be submitted 60 days af ter January 1 of each year will include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency i distributions of wind speed, wind direction, and atmospheric stability.

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside

{ the site boundary (Figures 5.1-1 and 5.1-2) during the report period. The j radioactive effluent relese report to be submitted 60 days af ter January I of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources.

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