ML19337A299

Proposed Revision to Radiological Effluent Tech Specs, Sections 1,2,3,4 & 6 Changing Data Analysis & Reporting Requirements

ML19337A299
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/05/1980
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19337A295	List: ML19337A294 ML19337A299
References
NUDOCS 8009090491
Download: ML19337A299 (50)

Text

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.J ATTACHMENT 1 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR ARKANSAS NUCLEAR ONE, UNIT 1 (REVISION 1) b009090h,'lf

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1.0 Definitions 1.9 Dose Equivalent I-131 The Dose Equivalent I-131 shall be concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose con-version factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

1.10 Source Check A Source Check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

1.11 Offsite Dose Calculation Manual (ODCM)

The Offsite Dose Calculation Manual shall contain the method-ology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the cal-culation of gaseous and liquid effluent monitoring alarm / trip setpoints.

1.12 ,

Gaseous Radwaste Treatment System A Gaseous Radwaste Treatment System is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.13 Ventilation Exhaust Treatment System A Ventilation Exhaust Treatment System is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing . venti-lation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing lodines or particu-lates from the gaseous exhaust stream prior to the releases 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.

1.14 Purge - Purging 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.

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1.15 Venting 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 Venting process'.

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3.5.6 Radiological Liquid Effluent Instrumentation f

Applicability: During releases via this pathway.

Objective: To provide instrumentation for radioactive liquid releases.

Specification:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.5.6-1 shall be operational with their alarm / trip setpoints set to ensure that the limits of Specification 3.22.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM).

3.5.6.1- With a radioactive liquif. effluent monitoring instrumen-tation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel not operational.

3.5.6.2 With one or more radioactive liquid effluent monitoring in-strumentation ' channels not operational, take the action shown in Table 3.5.6-1.

Bases:

The radioactive liquid efflu:.nt instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials i.n liquid effluents during actual or potential releases of liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with'the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

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Table 3.5.6-1 ,

Radioactive Liquid Monitoring Instrumentation Minimum Channels Instrument Operational Action

1. Gross radioactivity monitors providing automatic termination of -release

a. . Liquid Radwaste Effluent Line (1) A

2. Tiow Hate Measurement Devices

a. Liquid Radwaste Effluent Line (1) B

3. Tank Level Indicating Devices (for tanks out-side plant buildings)

a. Temporary Storage Tank Tg* (1) C

b. Temporary Storage Tank TB * (1) C

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• Applicable after tanks are installed 1

Table 3.5.6-l'(Continued)

-. Table Notation Action - Description A. . 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

a. At least two independent samples are analyzed in accordance with Specification 4.24.1.1 and

b. at least two technically qualified members of the facility staff independently verify the release rate computer input data and discharge line valving; After each 30 consecutive day period during which the requirement is not met, a Special Report will be sub-mitted within 30 days, detailing:

1. Identification of the equipment which is not operational and the reason for this,

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

3. Summary description of action (s) taken to prevent a recurrence Otherwise, suspend release of radioactive effluents via this pathway.

B. 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 estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.

After each 30 consecutive day period during which the requirement is not met, a Special Report will be submitted within 30 days.

This- report will include the three items listed in Action A above.

C. With the number of channels operable less than required by the minimum channels operable requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.

After each 30 consecutive day period during which the requirement is not met, Special Report will be submitted. within 30 days. This .

report will include the diree items listed in Action A above.

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-3.5.7 Radiological Gaseous Effluent Instrumentation Applicability: . Applies to the instrumentation listed in Table

'3.5.7-1.

Objective: To provide instrumentation for radioactive gaseous releases.

Specification:

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.5.7-1 shall be operational with their alarm / trip set-points set to ensure that the limits of Specification 3.23.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined

. in accordance with the ODCM.

3.5.7.1 With a radioactive gaseous effluent monitoring instrumenta-tion channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel not operational.

3.5.7.2 With one or more radioactive gaseous effluent monitoring instrumentation channels not operational, take the action shown in Table 3.5.7-1.

Bases:

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 of gaseous efflu-ents . The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm /

trip will occur prior to exceeding the limits of 10 CFR Part 20.

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Table 3.5.7-l' Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Channels Instrument Operable Action

1. Waste Gas Holdup System a .- Noble Gas Activity Monitor (1) A

b. ' Effluent System Flow Rate Measuring Device. (1) B

2. Reactor Building Purge System

a. Noble Gas Activity Monitor (1) D

b. Iodine - Sampler (1) E

c. Particulate Sampler ' (1) E

d. Flow Rate Monitor (1) B

e. Sampler Flow ' Rate Monitor (1) B

3. Auxiliary Building Ventilation System

a. Noble Gas Activity Monitor (1) C

b. Iodine Sampler (1) E

c. Particulate' Sampler (1) E

d. Flow Rate Monitor (1) B

e. Sampler Flow Rate Monitor (1) B

4. Spent Pool Area Ventilation System '

a. Noble Gas Activity _ Monitor (1) C

b. hdina Sampler (1) E

c. Peticulate Sampler (1) E

d. Flow Rate Monitor (1)_ B

e. Sampler. Flow Rate Monitor. (1) B l l

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Table 3.5.7-1 (Continued)

Table Notation Action Description A. 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:

.a. At least two independent samples of the. tank's con-tents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release

- rate computer input data and discharge valve lineup; After each 30 consecutive day period during which the requirement is not met, a Special Report will be sub-mitted, within 30 days, detailing:

1. Identification of the equipment which is not operational and the reason for this,

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

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

Otherwise, suspend release of radioactive effluents via this pathway.

B. With the number of channels operable less than required by the minimum channels operable re-quirement, effluent releases via this pathway may continue provided the flow rate is estimated at-least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

After each 30 consecutive day period during which the requirement is not met, a Special Report till be submitted within 30 days. This report will in-clude the three items listed in Action A above.

C. With the number of channels operable less than re-quired by the minimum channels operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Table 3.5.7-1 (Continued)

Table Notation Action Description After each 30 consecutive day period during which the requirement is not met, a Special Report will be sub-mitted within 30 days.' This report will include the three items listed in Action A above.

D. With the number of channels operable less than re-quired by the minimum channels operable requirement, immediately suspend purging of radioactive effluents via this pathway.

E. With the number of channels operable less thar. r1-quired by the minimum channels operable recuiranent, effluent releases via the affected pathway may con-tinue provided samoles are collected with auxilidry sampling equipment as required in Table 4.25-1.

After each 30 consecutive day period during which the requirement is not met, a Special Report will be sub-mitted within 30 days. This report will include the three items listed in Action A above.

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.- 1 3.22- Radioactive Liquid Effluents -

3.22.1.- - Concentration Applic5bility: . Applies for every release from the liquid radwaste system.

bjective

To ensure that the-limits of 10 CFR 20 are met.

Specifications:

3.22.1'.1 The concentration of radioactive material released from the site to unrestricted areas (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table ~II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or egtrained noble gases, the concentration shall Le Imited to 2 x 10 - microcuries/ml.

3.22.1.2 With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above-limits.

Bases:

.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, Column 2. This limitation provides additional assurance ~ that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the.

Section II.A design objecF.ves of Appendix I,10 CFR 50, to an individual and (2) the limits of 10 CJR 20.106(e) to the population.

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Radioactive Liquid Effluents 3.22.2 Dose Applicability: Applies to releases from the liquid radwaste

system.

Objective: To ensure that the dose limits of 10 CFR 50, Appendix I, Section IV. A are met.

Specificationy 3.22.2.1 The dose or dose commitment to an individual from radio-active materials in liquid effluents released from the site to unrestricted areas (see Figure 5.1-1) per unit shall be limited:

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.

3.22.2.2 With the calculated dose from the release of radioactive i materials in liquid effluents exceeding any of the above I limits, in lieu of any other report required by Specifi-cation 6.12.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.12.5, a Special Report <

which identifies the cause(s) for exceeding the limit (s) and defines the corrchie actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ.  !

Bases:

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 Condi-tion for Operation implements the guides set forth in Section II. A of Appendix I. The Action statements provide the required operating flexi-bility 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 cffluents will be kept "as low as is reasonably achievable."

This specification applies to the release of liquid effluents from each reactor at' the site. For units with shared radwaste treatment systems, i the liquid effluents from the shared system are proportioned among the units sharing that =ystem.

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1 Radioactive Liquid Effluents 3.22.3 Waste ~ Treatment Applicability: Applies when liquid radioactive waste must be dis-charged.

Objective: To assure that the amount of radioactive material in liquid effluents will be "as low as reasonably achiev-able. "

' Specifications:

3.22.3.1 The liquid radwaste treatment system shall be operational.

The appropriate portions of the system shall be used to reduce -

the radioactive materials in liquid wastes prior to their discharge when the projected-doses due to the liquid effluent discharge from the site to unrestricted areas (see Figure 5.1-1) per unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

3.22.3.2 With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.12.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.12.5 a Special Report which includes the following information.

1. Identification of the equipment which is not operational and the reason for this.

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

3. Summary description of action (s) taken to pre-vent a recurrence.

Bases:

, The Waste Treatment Specification for the liquid radwaste treatment ensures that this system will be available for use _whenever liquid effluents require treatment prior to release to the environment. The requirement 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 of 10 CFR Part 50 and the design objective given in Section II.D of Appendix I 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 dose design objectives set forth in Section II. A of Appendix I,10 CFR Part 50, for liquid effluents.

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Radioactive Liquid Effluents 3.22.4 . Liquid Holdup Tanks Applicability: During holdup of radioactive liquid effluents in the-tanks listed below.

Objective: To assure.that accidental releases from outdoor tanks will not exceed 10 CFR Part 20.

Specifications:

3.22.4.1 - The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tanks.

3.22.4.2 With the quantity of radioactive material in any of the above listed tanks 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 /> reduce the tank contents to within the limit.

Bases:

Restricting the quantity of radioactive material contained in the speci-fled tanks provides assurance that in the event of an uncontrolled re-lease of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2.

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m Radioactive Gaseous Effluents 3.23.1 Dose Rate Applicability: Applies for each radioactive gaseous release.

Objective: To ensure that the dose rate, at the unrestricted area boundary, from gaseous effluents will be within the annual dose limits of 10 CFR 20.

- Specifications:

3.23.1.1 The dose rate due to radioactive materials released in gaseous effluents from the site to unrestricted areas (see Figure 5.L-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr 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 /yr to any organ.

3.23.1.2 With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).

Bases:

This specification is provided to ensure that the dose at any time at the unrestricted area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for un-restricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column I.

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 to annual average concentrations exceeding the limits specified in Appendix B, Table'II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)). For individuals who may at times be within the unrestricted area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric dif-fusion factor above that for the unrestricted area boundary. The speci-  ;

fled _ release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding th',-

roid dose rate above limits also restrict, at~ all times, the correspond-ing thyroid dose rate above background to an infant via the cow-milk-in-fant pathway to less than or equal to 1500 mrem / year for the nearest cow to _the plant.

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i This -specification; applies to the' release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the: gaseous effluents from the shared system are proportioned among the units sharing the system.

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Radioactive Gaseous Effluents 3.23.2 - Dow - Noble Gases -

Applicability: Applies at all times -for radioactive gaseous re-leases.

- Objective: To ensure that the dose limits of 10 CFR 50. Appendix I,Section IV. A are met.

Spec'fications:

3. 2c . . 1 The air dose due to noble gases released in gaseous eftiuents from the site to unrestricted areas '(see Figure 5.1-3) per unit shall be limited to the following:

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.

3.23.2.2 With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.12.1, prepare and submit to the Commission within 30 days, pursuant to Specifi-cation 6.12.5, 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 noble gases in gaseous effluents during the remainder of the current calen-dar. quarter and during the subsequent three calendar quarters, so that the cumulative dose during these four calendar quarters is within (10) mrad for gamma radiation and (20) mrad for beta radiation.

Bases:

This specification is provided to implement the requirements of Section II.B, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condi-t tion for Operation implements the guides set forth in Section II.B of Appendix I. The Action statements provide the required operating flexi-bility 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 gaseous effluents will be kept "as low as is reasonably achievable".

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Radioactive Gaseous Effluents 3.23.3 -Dose - Radiciodine and Particulates

' Applicability: Applies at all times for radioactive gaseous re-leases.

Objective: To ensure that the dose limits of 10 CFR 50, Appendix I, Section IV. A are met.

Specifications:

3.23.3.1 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 the site to unrestricted areas (see Figure 5.1-1) per unit shall be limited to the following:

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

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

3.23.3.2 With the calculated dose from the release cf cualciodines, radioactive materials in particulate form, or radionuchdes (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 6.12.1, pre-pare and submit to the Commission within 30 days, pursuant to Specification 6.12.5, 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 radiciodines and radioactive materials in particulate form, and radio-nuclides (other than noble gases) wO half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar gaarter and during the subsequent three calendar quarters, so that the cumulative dose or I dose commitment to an individual from such releases during '

these four calendar quarters is within (15) mrem to any organ.

Bases:

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 Con-dition 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 Appen-dix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

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3.23.4 Gaseous Radwaste Treatment Applicability: Applies'when gaseous radioactive effluents

.must be discharged.

Objective: To assure that the amount of radioactive material in gaseous effluents is "as bw as reasonably achievable."

Specifications:

3.23.4.1 The gaseous radwaste treatment system.and the ventilation exhaust treatment system shall be operational when needed to treat gaseous radwaste. The appropriate portions of tl a gaseour radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluents air doses to un-restricted areas due to_ gaseous effluent releases from the site (see Figure =.1-1) per unit, when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radia-tion. The appropriate portions of the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) per unit when average over 31 days would exceed 0.3 mrem to any organ.

3.23.4.2 With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.12.1, prepare and submit to the Commission within 30 days, pursuant to Specifiction 6.12.5, a Special Report which includes the following information:

1. Identification of the equipment which is not operational and the reason for this,

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

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

Bases:

The Gaseous Radwaste Treatment -Specification for the gaseous radwaste system'and the ventilation exhaust treatment system ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gas-eous ' effluents will be kept "as low as is ' reasonably achievable". The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gas-eous effluents 66z

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Radioactive Gaseous Effluents 3.23.5 Gas Storage Tanks Applicability:  ; Applies at all times to the tanks in the gaseous radwaste holdup system.

Objective: To restrict the amount cf activity in a radio-active gas holdup tank.

Specification:

- 3.23.5.1.- The quantity of radioactivity contained in each gas storage tank shall be limited to less than'or equal to 15,480 curies noble gases (considered as Xe-133).

3.23.5.2 With the quantity of radioactive material in any gas storage 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 /> reduce the tank contents to within the limit.

Bases:

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individue?

at the nearest exclusion area boundary will be kept as low as is reason-ably achievable.

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i Radioactive Effluents 3.24.1 Total Dose Applicability: 'At all times.

Objective: -Limit total dose to less than the limits of 40 CFR 190.

Specification:

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3.24.1.1 The dose or dose commitment to any real individual from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any internal organ (except the thyroid,_ which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

3.24.1.2 With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the hmits of Specifications 3.22.2.1.a, 3.22.2.1.b, 3.23.2.1.a, 3.23.2.1.b, 3.23.3.1.a, or 3.23.3.1.b, in lieu of any other report required by Specification 6.12.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.12.2 within 30 days and limit the subsequent releases such that the dose or dose commitment to any real in-dividual from uranium fuel cycle sources is limited.to less than or' equal to 25 mrem to the total body or any internal organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to any real individual from uranium fuel cycle sources (:ncluding all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CPR Part 190 Standard.

Bases:

This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the re-sultant dose to a real-individual will exceed 40 CFR 190 if the in-dividual reactors remain within the reporting requirement level. The Special Report will describe a course of-action which should result in the limitation ~ of dose to a real individual'for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Reoort, it may be assumed that the dose commitment to the real individual from other uranium fuel' cycle sources is negligible, with the exception that dose contributions from other. nuclear fuel cycle facilities at the same site or within a radius of' 5 miles must be considered.

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-TABLE 4.24-1 Radioactive Liquid Waste Sampling and Analysis Program Minimum Lower Limit Sampling Analysis Type of Activity of Detection Liquid Release Frequency Frequency Analysis (LLD Type (pCi/ml)g P P A. Batch Waste Each Batch _ Each Batch Gamma Isotopic d 5x10-7 Release Tanks c f

I-131 lx10-6 P M Dissolved and lx10

-5 One Batch /M Entrained Gases (Gamma emitters)

P M H-3 lx10-5 Each Batch Composite b _

Gross Alpha lx10 '

P Q Sr-89, Sr-90 5x10-8 Each Batch Composite b Fe-55 Iv10'O P-32 lx10-j l

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- Table 1 (Continued) ~

-Table Notation

. a. The LLD is the smallest concentration of radioactive material-in a i t

^~

sample that will be detected with 95% probability with 5% probability

'of falsely _ concluding.that a blank observation represents a "real"

' signal.

- For 'a ~particular measurement ::ystem (which may' include radiochemical L separation):

LLD,=- 4.66 s b E . V '2.22 1(I Y exp (-Aot )

E Where:

LLD is the lower limit of detection as defined above (as microcurie

!- per unit mass or volume),

s is the standard deviation of the background counting rate or of

tNe' counting rate of a blank sample. It is W/t where N is the .

background count-and t is the counting time. The counting time (t). *

- is the same for both blank and sample.

+

i E is' the counting efficiency,

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

6 2.22 x 10 is the number of transformations per minute per j . microcurie,

. Y is t'he~ fractional radiochemical yield (when applicable),

A' is the radioactive decay constant for. the particular radio-

nuclide, and ,

at;is the elapsed time' between midpoint of sample _ collection or t-

. end.of sample ~ collection period and -time of, counting (for plant effluents, _ not' environmental samples).

The value'of sJused in the calculation of the LLD for a--

detection systeE shall be based on the actual 03::erved 1:

' variance of the background l counting rate or of the counting

~

rate of the blank samples '(as appropriate). In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the- background shall include the typical contributions'of

[ other radionuclides normally present-in the' samples. Typical

. values of E, V,- Y, and at'shall be used in the calcuation.

r

L Analyses shall_be-performed.in such.a manner that the stated

, LLD's will be' achieved under routine conditions.

-- 110z

-

g' r 4 , , , , - 4 ca. - ...- , .-,.,._.-_,. -

m. -,_,,_../.,,... -

Table 4.24-1 (Continued)

Table Notation

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 liquids released.

c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-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 measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as .being present at the LLD level for that nuc.lide. The "less than" values shall not be used in the required dose calculations.

D Daily P Prior to Release M Monthly Q Quarterly R Every 18 Months 110aa

Radioactive Liquid Effluents -

4.24.2 Dose Applicability: Applies to radioactive liquid releases.

- Objective: To ensure that the dose or dose commitment to an individual from radioactive liquid effluents is calculated. (See Specification 3.22.2)

Specifications:

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

Bases:

The dose calculations in the ODCM 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 equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in' Regulatory Guide 1.109. " Calculation of Annual Doses -to Man from Routine Releases of Reactor Effluents for the Pur-pose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, Octol ar 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dis-persior. cf Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April'1977.

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.

i 110bb 1

I l

Radioactive Liquid Effluents

~ 4.24.3 Waste Treatment

' Applicability: - Applies to1the-parts of the liquid radioactive waste treatment system which are normally.used to

_ process liquid radwaste.

Objective: To ensure that the liquid radwaste treatment system is operational.

Specification:

4.24.3.1- The liquid radwaste treatment system shall be demonstrated

- operational by operating the appropriate parts of the liquid radwaste treatment system equipment for at least 5 minutes at least once per 92 days unless the liquid radwaste system-has been utilized to process radioactive liquid effluents during the previous 92 days.

- Bases :

The operational status of the liquid radwaste. treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

4 110cc 4

n , .,

,,h , -

Radioactive' Liquid Effluent

-4.24 S Liquid Holdup Tanks-

' Applicability: During holdup of radioactive liquid effluents in the tanks listed in Specification 3.22.4.1.

Objective: To ensure that accidental releases from outdoor tanks will not exceed 10 CFR- Part 20.

Specification:

4.24.4.1 The quantity of radioactive material contained in each of the tanks listed in Specification 3.22.4.1 shall be determined to be within the specification limit by analyzing a repre-sentative sample of the tank's contents at least once per 7 days-when radioactive materials are being added to the tank.

Bases:

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncon-trolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2.

L 4

110dd

. 1

~

l

- _ _H

Radioactive Gaseous Effluents 4.25.1 Dose Rate Applicability: Applies for each radioactive' gaseous release.

Objective: To ensure that the dose rate, at any time, at the unrestricted area boundary from gaseous effluents will be within the annual dose limits of 10 CFR 20.

Specification:

4.25.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Specification 3.23.1.1 in accordance with the methods and procedures of the ODCM.

4.25.1.2 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Specification 3.23.1.1 in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.25.1.

Bases:

This specification provides for sampling and analyses to-ensure that Specification 3.23.1 is met.

l l

110ee

Table 4.25-1 Radioactive Gaseous Waste Sampling and Analysis Program ,

Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)

Gaseous Release . Type frequency Prequency . Activity Analysis (pCi/ml)a Gamma Isotopic d

-A. Waste Gas Storage ' Each " rank Each "fank lx10,4 Tank G Grab 11-3 1x10 Sample P P B. Ileactor Building - Each Purge Each Purge Gamma Isotopicd lx10-4 Purge Grab Sample .11-3 -lx10

-6 C. Unit Vents ),c d

.M M Gamma Isotopie lx10j (Auxiliary Bldg. Grab Sample 11-3 lx10 5 Spent Fuel Pool 4-ei - Area ventilation) 12 W 1-131 W Charcoal I-133 lx1010 lx10-Sample W Gamma Isotopicd lx10

-II Particulate (I-131, Others)

W Sample Q Gross Alpha ' lx10-II Particulate W . Sample

-II Q Sr-89, Sr-90 lx10 Particulate W Sample

Table 4.25-1 (Continued)

TABLE NOTATION

a. The .LLD is defined in Table Notation a. of Table 4.24-1 of Specification 4.24.1.1.

b. Tritium grab samples shall be taken at least once per 7 days when the refueling canal is flooded.

-c. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area when the ventilation system is in operation.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135, for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 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 shall not be reported as being present at the LLD level for that nuclide.

The "less than" values shall not be used in the required dose calculations.

D Daily P Prior to Release W Weekly M Monthly Q Quarterly R . Every 18-Months 110gg s

og s ,

l Radioactive Gaseous Effluents

-4.25.2 Dose, Noble Gaseous Applicability: Applies at all times for radioactive gaseous re-leases.

Objective: To ensure that the requirements of 10 CFR 50, Appendix I, Section III. A are met, and that the cumulative gaseous dose contributions are calculated.

Specifications:

4.25.2.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance v 1 the ODCM at least once every 31 days.

Bases:

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 ,nodels and data such that the actual ex aosure of an. individual through appropriate pathways is unlikely to be suastantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radio-active noble gases in gaseous effluents are consistent with the methodol-ogy provided in Regulatory Guide 1.109, " Calculation of Annual Doses to

' Man from Routine Releases of Reactor Effluents for the Purpose of Evalua-ting 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 determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

110hh

Radioactive Gaseous Effluents 4.25.3 Dose, Iodine and Particulates Applicability: Applies at all times for radioactive gaseous re-leases.

Objective: To ensure that the requirements of 10 CFR.50, Appendix I, Section III. A, are met and that the cumulative dose contributions of iodine and particulates are calcu-lated.

Specifications:

4.25.3.1 Dose Calculations Cumulative dose contributions from iodine and particulates in gaseous effluents for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once every 31 days.

Bases:

The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that confor-mance with the guides of Appendix I be shown by calculational procedures based on models and date, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underesti-mated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject material are 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 At-mospheric Transport and Dispersion of Gaseous Effluents in Routine Re-leases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

11011

Radioactive Gaseous Effluents 4.25.4 Gaseous Radwas'e Treatment Applicability: Applies to tla parts of the radioactive-weste treatment and plant ventilation filtration systems which are normally used to process gaseous wastes. This excludes the Reactor Building-Purge System.

Objective: To ensure that the gaseous radwaste treatment and ventilation filtration systems are operational.

Specifications 4.25.4.1 The gaseous radwaste treatment s" stem and ventilation exhaust system shall be demonstrated operational by operating the appropriate parts of the gaseous radwaste treatment system equipment and ventilation exhaust treat-ment system equipment for at least 5 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

Bases:

The operational status of the gaseous radwaste treatment system and the ventilation exhaust treatment system ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.

110jj

. O' O Rad'ioactive Gasecas Effluents

-4.25.5 Gas Storage Tanks Applicability: Applies to the tanks in the gaseous radwaste holdup system.

Objective: To ensure meeting the requirements of specification 3.23.5.

Specifications:

4.25.5.1 - The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limit of Specification 3.23.5.1 when radioactive materials have been added to the tank.

Bases:

This Specification is provided so that the requirements of Specification 3.23.5.1 can be met.

Il0kk l l

i

4.25.6 Radioactive Effluents 4.25.6.1 Total Dose Applicability: At all times.

Objective: Limit total dose to the limits of 40 CFR 190.

Specification:

4.25.6.1.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.24.2.1, 4.25.2.1, and 4.25.3.1 and in accordance with the ODCM.

Bases:

This specification is provided to meet the dose limitations of 40 CFR 19 0 . The specification requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents to unrestricted areas exceed twice the design objective doses of Appendix I. The Special Report will describe a course of action which should result in the limitation of dose to a real individual for 12 consecutive months to .within the e CFR 190 limits. For the purposes of the Special Report, it may be assumen ^"* +he dose commitment to the real individual from other uranium fuel y. iources is negligible, with the exception that dose contributions from of.er nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be con-sidered.

11011

7,

. e Radilogical Environmental Monitoring 4.26.1 Monitoring Program Applicabilitly: Applies at all times.

Objective: To provide information on the radiological effects of station operation on the environment.

Specifications:

4.26.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 4.26-1 and shall be analyzed pur-suant to the requirements of Tables 4.26-1 and 4.26-2. The sample locations shall be shown on a figure in the ODCM.

4.26.1.2.a. With the radiological environmental monitoring program not being conducted as specified in Table 4.26-1, prepare and submit to the Commission in the Annual Radio-logical Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. (Deviations are permitted from the required sampling schedule if specimens are not obtain-able due to hazardous conditions, seasonal unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.)

b. With the level of radioactivity in an environmental sampl-ing medium at one or more of the locations specified in Table 4.26-1 exceeding the limits of Table 4.26-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report which includes an evaluation of any. release conditions, environmental factors or other aspects which caused the limits of Table 4.26-3 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 condition shall be reported and des-cribed in the Annual Radiological Environmental Report.

c. With milk or fresh leafy vegetable samples unavail-able from any of the sample locations required by Table 4.26-1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.12.2.3 a report which identifies the cause of the unavail-110mm

ability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from Table 4.26-1 provided the

.. locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.

4.26.1.3 The results of analyses performed on the radio-

. logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Report. The Annual Radiological Environmental Report may be submitted with or as a part of the Annual Environmental Report required by Environ-mental Technical Specification 5.6.1.

Bases _:

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 effluents monitoring pro-gram by verifying that the measurable concentrations of radio-active materials and levels of radiation are not higher than expected on the basis of the effluent measurements and model-ing of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. . Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 4.26-2 are state-of-the-art for routine environmental measurements in industrial laboratories.

The LLD's for drinldng water meet the requirements of 40 CFR 141.

Il0nn I

4 Table 4.26-1

~

lladiological Environmental Monitoring Program Exposure. Pathway . Sampling and . Type and Frequency

'and/or Sample - ~ Sample Locations

• Collection Frequency Of Analyses

1. Airborne

a. lladiciodine . -(Locations 1-7)- Continuous operation of Radioiodine canister.

and Partic- sampler with sample col- Analyze at least once ulates lection as required by per 7 days for I-132.

dust loading but at least once per 7 days. Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

t Perform gamma . isotopic g analysis on each ~ sample o-when gross beta activity is > 10 times the mean of -

control sample. Perform gamma isotopic analysis on

, composite (by location) sample at least once per, 92 days.

2. .tlirect Radiation (Locations I-7) At least once per 92 Gamma dose. At least 2 dosimeters days. once per 92 days.

• Sample location are shown in the Offsite Dose Calculation Manual (0DCM).

A Table 4.26-1 Radiological Environmental Monitoring Program -

Exposure Pathway Sampling and Type and Prequency and/or Sample Sample Locations

• Collection Frequency Of Analyses

3. . Waterborne

~a . Surface ~ (Locations 8. and 10)- Monthly grab' sample collected once per -

Gamma isotopic analysis

. of each sample by loca-7

?! days.

tion. Tritium analysis of of composite sample at

, least once. per 92 days. -

b. Ground (Location 11 and 13) At least once per 92 days. Gamma isotopic and tritium analyses of each sample.

c. ' Drinking (Location 14)__ Monthly grab sample _ I-131 analysis of each sample; y

u and Gross beta and gamma iso-topic analyses of each sample. Tritium analysis of composite sample at least once per 9? 'ays.

d. Sediment (Location 8,10) At least once per 184 days., Gamma isotopic ' analysis imm of each sample Shoreline

• Sample location are shown in the ODCM.

t 4

Table 4.26-l' Radiological Environmental Monitoring Program

. Exposure Pathway _ .

Sampling and . Type and Frequency and/or ' Sample Sample ' Locations

• Collection Fruquency Of Analyses

4. Ingestion

a. Milk (Locations 19,- 20, 23, At least once' per 31 days Gamma isotopic and and

26) when animals are on pasture. I-131 analyses of each sample.

b '. ' Pish (Locations'8 and 10) One sample in season, . Gamma isotopic analysis or at least once per on edible. portions.

184 days if not seasonal.

One sample of each of the following species:

_,. 1. Catfish

.g 2. Crappie

. o

.c. Food ** (Locations 30, 31, 32) At time of harvest. One Gamma isotopic analysis Products sample of each of the on edible portion following classes of food products:

1. Fruits ~

2. Flowering Vegetable

3. Tubular Vegetable (Location 33) At time of harvest. One I-131 analysis.

sample of broad leaf vege-tation.

i

• Sample location are shown in the ODCM.

• • If these food products are available.

4 4

)

6

O Table 4.26-2 .

Maximum Values of the Lower Limits of Detection (LLD("))

Airborne Particulate

. . Water or. Gag Fish Milk Pood Products Sediment Analyses . (pCi/l) (pCi/m ) (pCi/kg, wet) {pCi/l) (pCi/kg, wet) (pCi/kg, dry) gross beta 4 (b) -1 x 10

-2 3 b 1I 12000: (1000 )

54 Mn '15 130 59 30 260 Pe 58,'60 -

15 130 C0 65 -30 2@

2n. ,

g 95Zr-N b 15

=131 3

1* 7 x 10 -2 1 60(C) 134, 137 Cs 15(10(b)), 18 1 x 10 -2 130 15 80 140 Ba-la 15 15

• For Monthly grab samples

Table 4.26-2 (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.

For a particular measurement system (which may include radio-chemical separation):

LLD = 4.66 s u E V -

2.22 Y eRp (- Aa t)

Where

' LLD is the lower limit of detection as defined above (as pCi per unit mass or volume).

sa is the standard deviation of the background counting rate or of the counting rate of a blank sample. It is ff/t where N is the background count and t is the counting time. The counting . time (t) is the same for both blank and sample.

E is the counting efficiency, V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie.

. Y is the fractional radiochemical yield (when appll-cable).

A is the radioactive decay constant for the particular radionuclide a t is the' elapsed time between sample collection or end of the sample collection period and time of counting.

The value of s u used in the calculation of the LLD for a detection syt im .shall be' based on the actual observed variance of the back-

. ground counting rate or of the counting rate of the blank samples (as appropriate). In calculating the LLD for a radionuclide deter-mined by gamma-ray spectrometry, the background shall include

.the typical contributions of other radio-nuclides normally pre- j sent in the samples. Analyses shall be performed in such a' l manner that the stated LLDs will be achieved under routine con-  !

. ditions.

b - LLD for drinking.

c - LLD for.lcafy vegetables.

' 110ss

3 S

This page left blank llott 1

.7 - _

?;s Table 4.26-3 Reporting I.evels For Radioactivity Concentrations In Fnvironmental Samples Reporting Levels Airborne Particulate Water or Gas .

Fish ' Milk Vegetables Analyses {pCi/l) (pCi/m ) (pCi/kg, wet) {pCi/l) (pCi/kg, wet)

.11-3 3 x 104 3

Mn-54 1 x 10 3 x 104 Fe-59 4 x 102 1 x 104 co-58 1 x 10 3 3 x 104

- C0-60 3 x 10 2 1 x 104 5

E Zn-65 3 x 10 2 2 x 104 2r-Nb-95 4 x 102 I-131 2 0.9 3 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 - 50 20 2 x 103 70 2 x ;0 3 13a-l.a-140 2 x 102 3 x 102 a

a .

Radiological Environmental Monitoring 4.26.2 Land Use Census Applicability: Applies at all times.

Objective: This specification will identify changes in use of the unrestricted areas.

Specifications:

4.26.2.1 A land 'use census shall be conducted and shall 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 from the ANO-1 reactor building.

4.26.2.2 The land use census shall be conducted at least once per 12 months between the dates of June I and October 1. by door-to-door survey, aerial survey, or by consulting local agriculture authorities.

4.26.2.3 a. With a land use census identifying a location (s) which yields a calculated does or dose commit-ment greater than the values currently being cal-culated in Specification 4.25.3.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.12.2.3, a report which identi-fies 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) greater than at a location from which samples are currently being obtained in accordance with Specification 4.26.1.2a prepare and submit to the Commission within 30 days, puc.suant to Specification 6.12.3.2, a report which identifies' the new location. The new location shall be added to the radiological. environmental monitoring program within 30 days, if possible. The sampling location having the lowest calculated dose or dose commitment (via the same exposure path'vay) may be deleted from this monitoring program after (October

31) of the year in _which this land use census was conducted.

4.26.2.4 - The results of the land use census shall be included in the Annual Radiological Environmental Report.

110vv

o .

d

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

Bases

This Specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the moni-toring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CPR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathway via leafy vegetables will be identified and monitored since a garden of this size is the' minimum required to produce the quantity (26kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by.a child.

To determine this minimun garden size, _ the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegeta-tion (i.e. , similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.

4 110ww -

O #

Radiological Environme: tal Monitoring 4.26.3 Interlaboratory Comparison Program Applicability: Applies to the off-site radiochemistry laboratory.

Objectives: To provide independent checks on the accuracy of the measurements of radioactive material in environmental samples.

Specifications:

4.26.3.1 Analyses shall be performed on radioactive materials supplied as part of Interlaboratory Comparison Program which has been approved by NRC.

4.26.3.2 With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.

4.26.3.3 The results of analyses performed as part of the above re-quired Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report pursuant to Specification 6.12.2.4.

Bases:

The requirement foc participation in an Interlaboratory Compari-son Program is provided to ensure that independent checks on the prec'sion and accuracy of the measurements of radioactive material in environmental sample matrices are performed as p art of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. '

110xx

~

'4.27 - Radioactive Effluent Instrumentation 4.27.1 Liquid Applicability: ' Applies to the instrumentation in the liquid radwaste system that is used to limit the amount of radio-activity released _ to.the environs.

Objective: To provide survehlance specifications for the in-struments required in Specification 3.5.6.

Specifications:

4.27.1.1 Each radioactive liquid effluent monitoring instrumentation .

channel shall be demonstrated operational by performance of the

. channel check, source check, channel calibration and channel test operations at the frequencies shown in Table 4.27.1-1.

4.27.1.2 The surveillance specification for the temporary tanks applies only after the tanks are installed.

Bases:

To ensure that the instrumentation for the liquid radwaste system is operational.

110yy

Table 4.27.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

• Channel Source Channel Channel

-Instrument- Check Check Calibration Test-

1. Gross Beta' or Gamma Radioactivity Monitors Providing Alarm and Automatic Termination

of Release

a. Liquid Radwaste Effluents Line D* P** R Q

2. Plow Rate Measurement Devices-

'a. Liquid Radwaste Effluent Line D* N.A R Q

'3. Tank Level Indicating Devices (for tanks outside the building)

a. Temporary Tank T3 D*** N.A. R Q y b. Temporary Tank T g D*** N.A. R Q N

Table Notation

• During releases via this pathway

• • Source check not required if the background activity is greater than the check source activity.

• • • During liquid additions to the tank.

4 4

. s.

4.27.2 Gaseous Applicability: Applies .to the instrumentation in the gaseous radwaste system that is used to limit the amount of activity released to the environs.

Objective: To provide surveillance specifications for the instru-ments listed in Specification 3.5.7.

Soecification:

4.-27.2.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operational by performance of the channel check,-source check, channel calibration and channel test operations at the frequencies shown in Table 4.27.2-1 Bases:

To ensure that.the instrumentation for the gaseous radwaste system is.

Operational, lloaaa

Table 4.27.2-1 ,

Radioactive Caecous Effluent Monitoring Instrumentation Surveillance Requirements.

L Channel _ Source- Channel . Channel -

l Instrument Check Check Calibration Test

1. Waste Gas lioldup System

a. Noble Gas Activity Monitor- P P R Q.

b. Iodine Sampler W N.A. N.A. N.A.

' c. Particulate Sampler ~ W N.A. N.A. N.A.

d. Flow Rate' Monitor P N.A. R Q

,.e. Sampler Flow Rate Monitor: D N.A. R Q

2. Reactor Building Purge System a '. Noble Gas Activity Monitor D P R Q'

b. Iodine Sampler W N.A. N.A. N.A-

c. Particulate Sampler W N.A N.A N.A

d. Flow Rate Monitor D N.A R- Q ,

e. Sampler Flow Rate Monitor D '

N.A. R Q

3. Auxiliary Building Ventilation System -

a. Noble Gas Activity Monitor D M R Q 0

b. Iodine Sampler W N.A. N.A. N.A.

c. ' Particulate Sampler W N.A. N.A. N.A.

d. Flow Rate Monitor D .

N.A. R Q

e. Sampler flow Rate Monitor. D N.A. R Q

. w.

, o, Table 4.27.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel source- Channel Channel t

Instrument Check - Check Calibration Test

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c. Sampler flow Rate Monitor D N.A. R Q R

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

h. Performance of special reviews, investigations and reports thereon as requested by the General Manager.

1. Review of the Plant. Security Plan and implementing procedures and shall submit recommended changes to the General Manager.

J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Generat Manager.

k. Review of every unplanned release of radioactive ma,er .41 to the environs; evaluate the event; specify remedial

. action to prevent recurrer.ce; and document the event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.

1. Review of all changes to the Offsite Dose Calculation Manual.

AUTHORITY 6.5.1.7.1 The Plant Safety Committee shall:

a. Recommend to the General 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 (c) above constitutes an unreviewed safety question.

6.5.1.7.2 In the event of a disagreement between the recommendations of ,

the Plant Safety Ccmmittee and the actions contemplated by_ the l General Manager, the course determined by the General Manager l to be more conservative will be followed. Records of the  ;

disagreement will be sent for review to the Director, Generation '

Operations, or Manager, Nuclear Operations and the Chairman of the Safety Review Committee by the General Manager on the next . working day.

RECORDS

6. 5.1. 8 The Plant Safety Committee shall maintain writte.. ,inutes of each meeting and copies shall be provided to the Chair-man of the Safety Review Committee by the General Manager.

6.5.2 Safe _ty Review Committee (SRC)

Amendment No. 37 - -123-l l

a . .-- 4.

FUNCTION.

6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a '. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry i

Amendment Nd. '37 - ' 123a--

- 1

- l,

.' 4 REVIEW '

6.5.2.7 The SRC shall review:

i a.- The safety evaluations for 1) cha w.ts to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constituto an unreviewed safety question.-

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.

c. Proposed tests or experiments which involve an un-reviewed safety question as defined in Section 50.59,10 CFR.

d. Proposed changes in Technical Specifications or licenses.

e. Violations of applicable statutes, codes, regu-lations, orders, Technical Specifications, license requirements, or of internal procedures or in-structions having nuclear safety significance.

f. Significant operating abnormalities or devia-tions from normal and expected performance of plant equipment that affect nuclear safety.

g. Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> noti-fication to the Commission.

.h. Reports and meeting minutes of the PSC.

1. Changes to the ODCM.

AUDITS 6.5.2.8 Audits-of facility activities shall be performed under the cognizance of the SRC. These audits shall en-compass:

a. The conformance of facility operation to pro-visions contained within the Technical Speci-fications and applicable license conditions at least once per year.

'b. The performance and retraining of all nembers of the plant management and operations staff, and the performance, training, and qualifications of new members of the entire plant staff at least once per year.

' Amendment No. 34 -125-

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a r c.. The results of all actions taken to correct deficiencies occurring in. facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.

d. The Facility Emergency Plan and implementing procedures at least once per two years.

e. The Facil'ity Fire Protection Program and implementing pro-cedures at least once per 24 months.

l i

Amendment No. 34 -125a-I L: -

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f. The Facility Security Plan and implementing procedures at least once per two years.

g. Any other area of facility operation considered appro-priate by the SRC or the Vice-President, Generation

& Construction .(VPG&C).

h. The radiological environmental monitoring program and the results thereof at least once per 12 months.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

6.5.2.9 Special Inspections and Audits A. An independent fire protection and loss prevention program inspection and audit shall be' aerformed at least once per

, 12 months utilizing either qua..ified offsite licensee per-sonnel or an outside fire protection firm.

AUTHORITY 6.5.2.10 The SRC shall report to and advise the Vice-President, Generation and Construction (VPG&C) within 30 days following each meeting.

' RECORDS 6.5.2.11 Records of JRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRC. meeting shall be prepared, approved and forwarded to the Vice-President, Generation & Con-struction (VPG&C) within 30 days following each meeting.

b. Reports of reviews encompassed by Section S.S.2.7.e,f,g and h above, shall be prepared, approved and forwarded to the Vice-President, Generation and Construction, (VPG&C) within 30 days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice-President, Generation

& Construction (VPG&C) and to the management posi-tions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 . The following actions shall be taken for Reportable

-Occurrences:

-126-

.. +

a. The Commission shall be notified and/or a repcrt sub-mitted pursuant to the requirements of Specification 6.12.

b. Each Reportable Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifi-cation to-the Commission shall be reviewed by the PSC and submitted to the SRC and the Manager, Nuclear.

Operations by the General Manager.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety Limit is violated:

a. The' facility shall be placed in at least hot shutdown with-in one hour,

b. The Nuclear -Regulatory Commission shall be notified and a repcrt submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.12.3.1.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the act.ivities referenced 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 equip-ment.

d. Sectr q Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. Offsite Dose Calculation Manual Implementation at the site.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and apprevEd by the General Manager prior to implementation and reviewer'. c :ritdically as set forth in administrative procedures.

6.8.3 Temporary changes to )_ ca 3 o'16.8.1 above may be made provided:

1

a. . The intent of the original procedure is not altered.

b. The change is approved by two members of the plant i staff, at-least one of whom holds a Senior Reactor l Operator's License on the unit affected.

TAmendment No. 37' -127-

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- c. ) The cha'nge'is documented, reviewed by the PSC and'

' approved by the General Manager within 14. days of -

. implementation'.

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127a-r-

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o i The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at lert 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.-

6.12.2.3 Monthly Operating Report Routine reports of operating statistics which include:

(1) Average Daily Unit Power Level (2) Operating Date Report (3) Unit Shutdowns and Power Reductions (4) Narrative Summary of Operating Experience (5)* Changes to the Offsite Dose Calculation Manual (ODCM)

Shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, by the fifteenth of each month following the calendar month covered by the report.

6.12.2.4 Annual Radiological Environmental Report *

(a) . Routine radiological environmental reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of the year following initial criticality.

(b) The annual radiological environmental reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environ-mental surveillance activities-for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the land use census required by Speci-fication 4.26.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the pro-blem and a planned course of action to alleviate the problert.

• Changes to the ODCM shall be submitted within 90 days from when the change was made effective.

+A single submittal may be made for ANO-1 and ANO-2. The submittal should combine those sections tht are common to both units at the station. .This submittal may be combined with the report required by Environmental ~ Technical Specification 5.6.1.

141

. )

6.12.3 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC as required below.

Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected oc supplemental reports, a licensee event eport shall be completed and reference shall be made to the ori-ginal report date.

6.12.3.1 Prompt Notification With Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. A copy of the confirmation and a written fellowup report shall also be sent to the Director, Office of Management Information and Program Control, USNRC. 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 narra-tive material to provide complete explanaticn of the circumstances sur-rounding the event.

(a) Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or failure to complete the required protective function.

NOTE:

Instrument drift discovered as a result of testing need not be reported under this item but may be reportable under items (e), (f), or 6.12.3.2(a).

i 142

4= )

(d)1 Abnormal degradation of systems other than those specified in item 6.12.3.1(c) above designed' to contain radioactive material resulting from the fission process.

NOTE:

Sealed sources or calibration sources are not included under this item. Leakage of valve packing or gaskets within the limits for identified leakage set forth in Technical' Specifications need not be reported under this item.

-(e) An unplanned.offsite release of 1) more than 1 curie of radioacitve material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or

3) more than 0.05 curies of radiciodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:

-1. - A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

(f) Occurrence of radioactive material contained in liquid or gaseous holdup tanks in excess of that permitted by the limiting condition for operation established in-the technical specifications.

(g) Any report (s) required by Specification (s) 3.22, t

3.23, 4.24, 4.25, and 4.26, except those reports described in Specification 6.12.2.

(h) Measureci levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 4.26-3 when averaged over any calendar quarter sampling period.

When radionuclides other than those in Table 4.26-3 are-detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits'of Specifications 3.22.2.1, 3.23.2.1 and 3.23.3.1.

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

145

. b-l 6.12.5 Special Reports.

. Special reports shall~be submitted to the Director of the Office of

-Inspection and Envorcement Regional Office within the time' period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements

-of the applicable reference specification:

a. Radiological Liquid Effluent Instrumentation, Specification 3.5.6.

b. Radiological Gaseous Effluent Instrumentation, Specification 3.5.7

c. Radioactive Liquid Effluents, Specifications 3.22.2 and 3.22.3.

d. _ Radioactive Gaseous Effluents, Specifications 3.23.2, 3.23.3, and 3.23.4.

e. Total Dose, Specification 3.24.1.

147

, p' 6.13 'fsite Dose Calculation Manual (ODCM) 6.13.1 'iae ODCM shall dercribe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous-and liquid effluents and in the calculation of gaseous

~

and liquid effluent monitoring instrumentation alarm / trip' setpoints consistent with the applicable LCO's contained'in

- these Technical. Specifications.

'6.13.2 Changes to the ODCM made by the licensee shall:

1. Be reviewed and found acceptable by the PSC and SRC.*

2. Be submitted to the Commission by inclusion in the Mon +hly Operating Report pursuant to Speci-fication 6.12.2.3 within 90 days of the date the change (s) was made effective and shall contain:

a. sufficiently detailed information to totally support the rationale for the change. Information submitted should' consist of a package of those pages of the ODCM to be changed with each page numbered and provided together with appropriate analyses or evaluations justifying the change (s);

b. a determination that the change will not reduce the accuracy or reliability _ of dose calculations or setpoint deter-minations; and

3. Shall become effective upon a date specified and agreed to by both the PSC and SRC following their review and acceptance -

of the change (s).

• Changes to the locations of environmental sampling stations, required by Specification 4.26.1, shall not require review by the PSC and SRC prior to- implementation.

s 148

e i The annual radiclogical environmental reports shall include summarized and tabulated results in the format of Table 6.12-1 of all radiological environmental samples taken during the re-port 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. The missing data shall be submitted as soon as possible in a supple-mentary report.

The report shall also include the following: a summary des-cription of the radiological environmental monitoring program

-including sampling methods for each sample type, size and physical characteristics of each sample type, sample prepara-tion methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving dis-tances and directions from one reactor; the result of land use census required by the Specification 4.26.2, and the results of licensee participation in the Interlaboratory Comparison Pro-gram required by Specification 4.26.3.

6.12.2.5 Semiannual Radioactive' Effluent Release Report **

(a) 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 data of initial criticality.

(b) The radioactive effluent release reports shall in-clude a summary of the _ quantities of radioactive liquid and gaseous effluents and solid waste release from the unit. The data will be summarized on a quarterly basis following the format of Regulatory Guide 121, Rev. O Appendix A.

(c) The radioactive effluent release reports shall include the following information for all un-planned releases to unrestricted areas of radio-active materials in gasecus and liquid effluents:

1. A description of the event and equipment involved. I 1

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

• • A single submittal may be made for ANO-1 and ANO-2.

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