ML13317A037

Amend 84 to Provisional License DPR-13,consisting of Proposed Change 83 to Tech Specs,Incorporating Radiological Tech Specs Necessary to Implement 10CFR50 App I Requirements Into Tech Specs App a

ML13317A037
Person / Time
Site:	San Onofre
Issue date:	09/12/1979
From:	James Drake, John Thomas Southern California Edison Co
To:
Shared Package
ML13317A038	List: ML13317A037 ML13317A039 ML13322A583
References
NUDOCS 7909240248
Download: ML13317A037 (82)

Text

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON

)

COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY )

for a Class 104(b) License to Acquire,

)

DOCKET NO. 50-206 Possess, and Use a Utilization Facility as

)

Part of Unit No. 1 of the San Onofre Nuclear )

Amendment No. 84 Generating Station SOUTHERN CALIFORNIA EDISON COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY, pursuant to 10 CFR 50.90, hereby submit Amendment No. 84.

This amendment consists of Proposed Change No. 83 to the Technical Specifications incorporated in Provisional Operating License No. DPR-13 as Appendices A and B. Proposed Change No. 83 is a request to incorporate radiological effluent technical specifications which implement the requirements of 10CFR50 Appendix I into Appendix A of the Technical Specifications.

In the event of conflict,,the information in this Amendment No. 84 supersedes the information previously submitted.

In our opinion, the proposed change does not result in a condition which significantly alters the impact of San Onofre Unit 1 on the environment, and there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change.

Pursuant to 10 CFR 170.22, Proposed Change No. 83, submitted as Amendment No. 84, is determined to be a Class III change.

The basis for this determination is that the Change involves the issue of incorporating the guidelines of 10CFR50 Appendix I into the existing Technical Specifications and does not involve a significant hazard.

4D94

-2 Accordingly, the fee of $4,000.00 corresponding to this determination is remitted herewith as required by 10 CFR 170.22.

Subscribed on this /_-

day ofA 1979 Respectfully submitted, SOUTHERN CALIFORNIA EDISON COMPANY By 6

1qZ J. H. Erike Vice Presidenj Subscribed and sworn to before me this

/c2 day of m

Notary Public in an or the County of Los Angeles, State oY California My Commission expires /_i_ day Charles R. Kocher James A. Beoletto of McSI Attorneys for Southern Cal fornia Edison pany OFFICIAL SEAL By DONA MARY WILCOMB:

NOTARY PUBLIC-CALIFORNIA James A. Bole t PRINCIPAL OFFICE IN

1. ov LOS ANGELES COUNTY

• My Commission Expires June 18, 1981

-3 Subscribed on this o

day of S6R ord0- /.79 Respectfully submitted, SAN DIEGO GAS & ELECTRIC By El1ectric Division David R. Pigott Samuel B. Casey Chickering & Gregory Attorneys for San Diego Gas & Electric Company By David R. Pigott Subscribed and sworn to before me this day ofS'yM bp(

My Commission expires the 1 day of Notary Public iA and for the Couoy of San Diego, State of California Angela B. Snyder OFFICIAL SEAL ANGELA B. SNYDER 5

i !OTARY PUBLIC - CALIFORNIA Principal Office. San Diego Co. Calif.

SMy Commission Exp. July 25, 10881

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of SOUTHERN

)

CALIFORNIA EDISON COMPANY

)

and SAN DIEGO GAS & ELECTRIC )

Docket No. 50-206 COMPANY (San Onofre Nuclear )

Generating Station Unit No. 1)

CERTIFICATE OF SERVICE I hereby certify that a copy of Amendment No.

84 was served on the following by deposit in the United States Mail, postage prepaid, on the

/1M day of 1979.

Henry J. McGurren, Esq.

Staff Counsel U. S. Nuclear Regulatory Commission Washington, D.C. 20545 David R. Pigott, Esq.

Samuel B. Casey, Esq.

Chickering & Gregory Three Embarcadero Center San Francisco, California 94111 I. R. Caraco Bechtel Corporation P. 0. Box 60860, Terminal Annex Los Angeles, California 94111 Michael L. Mellor, Esq.

Thelen, Marrin, Johnson & Bridges Two Embarcadero Center San Francisco, California 94111 Huey Johnson Secretary for Resources State of California 1416 Ninth Street Sacramento, California 95814 Janice E. Kerr, General Counsel California Public Utilities Commission 5066 State Building San Francisco, California 94102

-2 J. Rengel Atomic Power Division Westinghouse Electric Corporation Box 355 Pittsburgh, Pennsylvania 15230 A. E. Gaede P. 0. Box 373 San Clemente, California 92672 Frederick E. John, Executive Director California Public Utilities Commission 5050 State Building San Francisco, California 94102 Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C. 20555 James A. Beo etto Assistant Counsel Southern California Edison Company

DESCRIPTION OF PROPOSED CHANGE AND SAFETY AND ENVIRONMENTAL ANALYSIS PROPOSED CHANGE NO. 83 TO TEE TECHNICAL SPECIFICATIONS PROVISIONAL OPERATING LICENSE DPR-13 This is a request to revise the Technical Specifications of Appendix A and B.

REASON FOR PROPOSED CHANGE This proposed change would incorporate the radiological effluent technical specifications necessary to implement the requirements of 10CFR50 Appendix I into the Appendix A Technical Specifications of the San Onfore Unit 1 operating license.

This proposed change would also delete the existing radiological environmental monitoring technical specifications from the Appendix B Technical Specifications of the San Onfore Unit 1 operating license.

EXISTING SPECIFICATIONS The existing technical specifications are as constituted in the Appendix A and B Technical Specifications for San Onfore Unit 1.

PROPOSED SPECIFICATIONS To Appendix A, Section 1.0, Definitions, the following would be added:

SOURCE CHECK A SOURCE CHECK is the qualitative assessment of a channel response when the channel sensor is exposed to a radioactive source.

-2 OFFSITE DOSE CALCULATION MANUAL (ODCM)

An OFFSITE DOSE CALCULATION MANUAL (ODCM) is a manual containing 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.

Requirements of the ODCM are provided in Specification 6.12.

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.

VENTILIATION EXHAUST TREATMENT SYSTEM 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 adsorbers and/or HEPA filters for the purpose of removing iodines or particu lates 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.

FREQUENCY NOTATION The FREQUENCY NOTATION is specified in Table 1-1.

-3 MAJOR CHANGES TO RADWASTE SYSTEM MAJOR CHANGES to the radioactive waste systems (liquid and gaseous) are the modifications of process equipment, components, structures and effluent monitoring instrumentation which could significantly alter the characteristics and/or quantities of effluents released, invalidate the accident analyses or result in a significant increase in occupational exposure of personnel.

-4 TABLE 1.1 FREQUENCY NOTATION.

NOTATION FREQUENCY~l)

S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed Prior to each release.

N.A.

Not applicable.

1) For each frequency the allowable extension is 25%.

The total allowable extension for three consecutive frequency intervals is 3.25 times the interval.

-5 To Appendix A, Specification 3.5, Instrumentation and Control, the following Specifications 3.5.3 and 3.5.4 will be added:

3.5.3 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION Applicability:

As shown in Table 3.5.3.1 Objective:

Monitor and control radioactive liquid effluent releases.

Specification:

A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.5.3.1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded.

B. Action

1. With a radioactive liquid effluent monitoring instru mentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.15.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.5.3.1.

-6 Basis:

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases.

The alarm/trip setpoints for these instruments are calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

0 TABLE 3.5.3.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent Line (1) 1

b. Steam Generator Blowdown (1) 2 Effluent Line

2. Flow Rate Measurement Devices.

a. Liquid Radwaste Effluent Line (1) 3

b. Circulating Water Outfall**

(1) 3

c. Steam Generator Blowdown Effluent**

(1) 3 Line

• • Pump status, valve turns or calculations are utilized to estimate flow.

-7 TABLE 3.5.3.1 (Continued)

TABLE NOTATION

• During releases via this pathway.

ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:

1. A sample is analyzed in accordance with Specification 4.5.1.C.,

and;

2. At least two technically qualified persons verify the release rate calculations and discharge valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 With the number of channels -OPERABLE less than required by The Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 uCi/gram;

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

2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is < 0.01 uCi/gram DOSE EQUIVALENT 1-131.

-8 ACTION 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days 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.

If pump status, valve turn curves or calculations are used to determine flow, this action is not necessary.

-9 3.5.4' RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Applicability:

As shown in Table 3.5.4.1 Objective:

Monitor and control radioactive gaseous releases.

Specification:

A. The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.5.4.1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.16.1 are not exceeded.

B.

Action

1. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.16.1 are met, declare the channel inoperable.

2. With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.5.4.1.

Basis:

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radio active materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments are calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

TABLE 3.5.4.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION

1. Stack Monitoring System1

a. Gross Activity Monitor (1)

Radioactivity Rate 1

Measurement

b. Noble Gas Activity Monitor (1)

Radioactivity Rate 2

Measurement

c. Iodine Sampler Cartridge (1)

Verify presence of 3

cartridge

d. Particulate Sampler Filter (1)

Verify presence of 3

filter

e. Stack Fan Flow Indication (1)

Verify stack fan 4

operation

f. Sampler Flow Rate Measuring (1)

Sampler Flow Rate 5

Device Measurement

,1. Includes the following subsystems:

a) Spent Fuel Building Ventilation, Auxiliary Building Ventilation, and Waste Gas Treatment (CVI)

Building Ventilation Systems.

b) Containment Monitoring System.

c) Air Ejector System.

-10 TABLE 3.5.4.1 (Continued)

TABLE NOTATION

• During releases via this pathway.

ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases may continue if instruments 1b, c, and d are operable, otherwise take ACTION shown for 1b, c or d.

ACTION 2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of a waste gas tank may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that prior to initiating the release:

1. A sample of the tank's contents is analyzed, and

2. At least two technically qualified persons verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

-11 ACTION 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the end of sample collection.

ACTION 4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the fan operability is verified at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 5 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases may continue if instrument la is operable, otherwise declare instruments 1b, c and d inoperable and take ACTION shown for 1b, c and d.

-12 To Appendix A, Technical Specifications 3.15, Radioactive Liquid Effluents, 3.16, Radioactive Gaseous Effluents, 3.17, Dose and 3.18, Radiological Environmental Monitoring will be added:

3.15 RADIOACTIVE LIQUID.EFFLUENTS 3.15.1 Liquid Effluents Concentration Applicability:

At all times Objective:

Maintain the concentration of radioactive liquid material released from the site below 10CFR20 limits.

Specification:

A. The concentration of radioactive material released at anytime from the site to unrestricted areas (see Figure 3.15.1.1) shall be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 uCi/ml total activity.

B. Action:

With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore concentration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.2a.

-13 Basis:

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 10CFR Part 20, Appendix B, Table II.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I, 10CFR Part 50,.to an individual and (2) the limits of 10CFR Part 20.106(e) to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concen tration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

3.15.2 Liquid Effluent Dose Applicability:

At all times Objective:

Maintain the release of radioactive liquid effluents from the site as low as is reasonably achievable.

Specification:

A. The dose or dose commitment to an individual from radio active materials in liquid effluents released to unrestricted areas (see Figure 3.15.1.1) shall be limited:

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

2. During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

FIGURE 3.15.1.1 SAN ONOFRE NUCLEAR GENERATING STATION

'Sco CAMP JOsfp PENDLETON NAVAL RE SE RvAT ION ETEOROLOGCAL INSTRUMENTATION TOWER A

C FIC 0 C E A N

-14 B.

Action:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3d, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average 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.

Basis:

This specification is provided to implement the requirements of Sections II.A and IV.A of Appendix I, 10CFR Part 50.

Speci fication A implements the guides set forth in Section II.A of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable".

3.15.3 Liquid Waste Treatment Applicability:

At all times Objective:

Maintain radioactive releases from the site as low as is reasonably achievable by use of the liquid radwaste treatment system.

-15 Specification:

A. The liquid radwaste treatment system shall be OPERABLE.

The system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge from the liquid radwaste treatment system when the projected. dose due to liquid effluent releases to unrestricted areas (see Figure 3.15.1.1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

B. Action:

With radioactive liquid waste being discharged from the liquid radwaste treatment system without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3d, a Special Report which includes the following information:

1. Identification of equipment or subsystems not operable and the reason for inoperability.

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

3.

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

Basis:

The OPERABILITY 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

-16 environment.

The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."

This specifica tion implements the requirements of 10CFR Part 50.36a and design objective Section II.D of Appendix I to 10CFR Part

50.

The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effluents.

01

3.16 RADIOACTIVE GASEOUS EFFLUENTS 3.16.1 Dose Rate Applicability:

At all times Objective:

Maintain the dose rate at the exclusion area boundary from radioactive gaseous effluents within 10CFR20 limits.

Specification:

A. The dose rate, at any time, in the unrestricted areas (see Figure 3.15.1.1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

1. The dose rate limit for noble gases shall be

< 500 mrem/yr to the total body and < 3000 mrem/yr to the skin, and

2. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be < 1500 mrem/yr to any organ.

B. Action:

With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the limit(s) given in Specification A and provide prompt notification to the Commission pursuant to Specification 6.9.2.a.

-18 Basis:

This specification is provided to ensure that the dose rate at anytime at the exclusion area boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the cor responding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to (500 mrem/year to the total body or to <3000 mrem/year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to (1500 mrem/year for the nearest cow to the plant.

3.16.2 Dose, Noble Gases Applicability:

At all times Objective:

Maintain the dose due to noble gases in gaseous effluents as low as is reasonably achievable.

-19 Specification: A. The air dose in unrestricted areas (see Figure 3.15.1.1) due to noble gases released in gaseous effluents shall be limited to the following:

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

2. During any calendar year, to < 10 mrad for gamma radiation and <.20 mrad for beta radiation; B. Action:

With the calculated air dose from radioactive noble gases in gaseous effluents exeeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3d, 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 calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

Basis:

This specification is provided to implement the requirements of Sections II.B and IV.A of Appendix I, 10 CFR Part 50.

Specification A implements the guides set forth in Section II.B of Appendix I. Specification B provides the required operating flexibility and at the same time implements the

-20 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."

3.16.3 Dose, Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Other than Noble Gases Applicability:

At all times Objective:

Maintain the dose due to radioiodines, radioactive material in particulate form and radionuclides other than noble gases in gaseous effluents as low as is reasonably achievable.

Specification:

A. The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 3.15.1.1) shall be limited to the following:

1. During any calendar quarter to < 7.5 mrem to any organ; and

2. During any calendar year to < 15 mrem to any organ B. Action:

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3d, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken

-21 to reduce the releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 15 mrem to any organ.

Basis:

This specification is provided to implement the requirements of Sections II.C and IV.A of Appendix I, 10 CFR Part 50.

Specification A is the guide set forth in Section II.C of Appendix I. Specification B provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

3.16.4 Gaseous Radwaste Treatment Applicability:

At all times Objective:

Maintain radioactive gaseous releases from the site as low as is reasonably achievable by use of the gaseous radwaste and ventilation exhaust treatment systems.

Specification:

A. The gaseous radwaste treatment system and the ventilation exhaust treatment system shall be OPERABLE. The gaseous radwaste treatment system shall be used to reduce radio active materials in gaseous waste prior to their discharge

-22 when the projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas (see Figure 3.15.1.1) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation and 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 to unrestricted areas (see Figure 3.15.1.1) when averaged over 31 days would exceed 0.3 mrem to any organ.

B. Action:

With gaseous waste being discharged for more than 31 days without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3d, a Special Report which includes the following information:

1. Identification of equipment of subsystems not OPERABLE and the reason for inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE STATUS.

3.

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

Basis:

The OPERABILITY 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.

The

-23 requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, and design objective Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3.16.5 Gas Storage Tanks Applicability:

At all times Objective:

Limit the amount of radioactivity contained in gas storage tanks.

Specification:

A. The quantity of radioactivity contained in each gas storage tank shall be limited to < 56,000 curies noble gases (considered as Xe-133).

B. Action:

With the quantity of radioactive material in any one 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 /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.2a.

The written followup 01 report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

Basis:

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure."

3.17 DOSE Applicability:

At all times Objective:

Maintain the dose due to the release of radioactive materials within specified limits.

Specifications: A. The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of 12 consecutive months.

B. Action:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.2.A, 3.16.2.A or 3.16.3.A, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3d and limit the subsequent

-25 releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to *< 25.mrem to the total body or any organ (except thyroid, which is limited to < 75 mrem) over 12 consecutive months. This report shall include an analysis which demonstrates that radiation exposures to all real individu als from all uranium fuel cycle sources (including 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 CFR Part 190 Standard.

Basis:

This specification is provided to meet the reporting require ments of 40 CFR 190.

In complying with 40 CFR 190, nuclear fuel cycle facilities over five miles away are not considered to contribute to the dose assessement.

3.18 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.18.1 Monitoring Program Applicability:

At all times Objective:

Monitor exposure pathways for radiation and radioactive material.

Specification:

A. The radiological environmental monitoring program shall be conducted as specified in Table 3.18.1.

-26 B.

Action:

1. When the radiological environmental monitoring program is not being conducted as specified in Table 3.18.1..prepare and submit to the Commission, in the Annual Radiological Operating 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 sched-ule if specimens are unobtain able due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.)

2. When the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.18.1 exceeds the limits of Table 6.9.2.1 when averaged over any calendar quarter, prepare and submit to the Commis sion within 30 days of the determination, a report which includes an evaluation of any release conditions, environ mental factors or other aspects which caused the limits of Table 6.9.2.1 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 described in the Annual Radiological Environmental Operating Report.

TABLE 18.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

1. AIRBORNE

a. Radioiodine and (1)

Continuous 7 day samples Gross beta at least Particulates 72 hrs. after col lection weekly.

Gamma spectrum analysis if above IpCi/m 3.

Filters composited quarterly for gross alpha, gamma spectrum and radiostrontium analyses.

Charcoal filters analyzed for 1-131 within 8 days of collection by gamma spectrum analysis.

2. DIRECT RADIATION (1)

Four CaSO4 (Dy) TLD's at Gamma dose quarterly each station collected quarterly. Two LiF TLD's at each station collected annually.

3.

WATERBORNE

a. Ocean Water (2)

Bimonthly Gross beta bimonthly.

Gamma spectrum for Cs-137 if gross beta greater than 30 pCi/1.

Radio strontium analysis if Cs-137 is present. Tritium semiannually on composited samples.

(1) See Figure 3.18.1 (2) See Figure 3.18.2

0 0a TABLE 3.18.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

b. Drinking Water (1)

Samples collected monthly Gross beta and gross at each station.

alpha monthly on filtrate and solids.

Tritium on filtrate.

Gamma spectrum analysis for Cs-137 and 1-131 if gross beta above 30 pCi/l.

Radiostrontium analysis if Cs-137 above 200 pCi/l.

Composited quarterly for gross beta and gross alpha on filtrate and solids and tritium on filtrate. &

c. Beach Sand (2)

Semiannually.

Gamma spectrum analysis semiannually.

d. Ocean Bottom (2)

Semiannually.

Gamma spectrum Sediments analysis semiannually.

4. INGESTION

a. Nonmigratory (2)

Semiannually. Each sample Gamma and tritium marine animals will include:

analyses of each species flesh quarterly.

1. Fish -

2 adult species If Cs-137 levels above such as perch 6nCi./Kg radiostron and sheepshead.

tium analysis will be performed..

(1) See Figure 3.18.1 (2) See Figure 3.18.2

TABLE 3.18.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

2. Crustaceae -

such as crab or lobster

3. Mollusks -

such as seahares Representative vegetables

b. Local Crops (1) normally 1 leafy and 1 fleshy Gamma, tritium and collected at harvest time.

radiostrontium At least 2 vegetables semi-analyses twice per annually from each station.

year.

c. Kelp (2)

Semiannually.

Gamma and tritium analysis semiannually.

5. OTHER

a. Soil Sampling (1)

Annually Gamma and radiostron-I tium analyses annually.

b. Jack Rabbit (1)

Semiannually.

Thyroid analyzed Sampling for 1-131; Femur analyzed for Sr-90 and 89 levels; and gamma spectrum analysis of flesh semiannually.

(1) See Figure 3.18.1 (2) See Figure 3.18.2

-LEGEND DIRECT RADIATION STATIONS Dona 0 ( THRu 1s)

L DRINKING WATER (1) 0 LOCAL CROPS (I/2) 0 JACKRABBITS (I)

.CAMP O SOL SAMPLES 1,2,3 6 5)

O PARTICULATE AIR o

SAMPLERS (I THRU 3)

SAN ONOFRE SITE (ID STATION 2

LOCATED SMI SSE OCEANSIDE.

II 0

5 SCALE IN MILES SAN ONOFRE OCEANSIDE NUCLEAR.GENERATING STATION UNIT I

FIGURE 3.8.1 TERRESTRIAL MONITORING FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

UNIT.I SOUTH BOUNDARY B

Or STATE PARK E

6 CO 12 SAN MATEO KELP BED GOUTFALL A,24 BARN KELP BED 6-INTAKEI 30 3Qc OC F

A -

OCEAN WATER SAMPLE B -

BEACH SAND SAMPLES C -

OCEAN BOTTOM SEDIMENT SAMPLES D - ZONE FOR CRUSTACEA SAMPLING SAN ONOFR& KELP BED E -

ZONE FOR MOLLUSK SAMPLING F -

ZONE FOR FISH a SEAHARE SAMPLING 42 G -

KELP SAMPLES O

1000 2000 3000 4000 FEET FIGURE 3.18.2 OCEANOGRAPHIC MONITORING STATIONS FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

26f HUNTINGTON BEACH CONTROL STATION CONTROL STATION NEAR NEWPORT 1EACH SAN ONOFRE NUCLEAR GENERATING STATION 11,1 OCEANSIDE CONTROL STATION 0

0 5

10 20 APPROXIMATE SCALE IN MILES FIGURE 3.18.3 CONTROL STATIONS FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

-27

3. When fresh leafy vegetable samples are unavailable from any of the sample locations required by Table 3.18.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.3e a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replace ment samples. The locations from which samples were unavailable may then be deleted from Table 3.18.1 provided the locations from which the replacement samples were obtained are added.to the environmental monitoring program as replacement locations, if avail able.

Basis:

The radiological monitoring program required by this specifi cation provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionu clides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

3.18.2 Land Use Census Applicability:

At all times

-28 Objective:

Monitor the unrestricted area surrounding the site for potential changes to the radiological monitoring program as necessary.

Specification:

A. 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 9 landward meteorological sectors within a distance of five miles.

B. Action:

1. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.6.3, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3e, a Special Report which identifies the new location(s).

2. 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 3.18.1, prepare and submit to the Com mission within 30 days, pursuant to Specification 6.9.3e, a Special 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

-29 calculated dose or dose commitment (via the same, exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Basis:

This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

3.18.3 Interlaboratory Comparison Program Applicability:

At all times Objective:

To ensure laboratory analysis of radiological environmental monitoring samples is correct and accurate.

e

-30 Specification:

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

B. 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 Operating Report.

Basis:

The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environ mental monitoring in order to demonstrate that the results are reasonably valid.

In Appendix A, Specification 4.1, Operational Safety Items, will be revised as follows:

4.1 EQUIPMENT, INSTRUMENTATION AND SAMPLING 4.1.1 Operational Safety Items Tables 4.1.1 and 4.1.2 will be changed to tables 4.1.1.1 and 4.1.1.2. Specifica tions 4.1.2, Radioactive Liquid Effluent Instrumentation, and 4.1.3, Radioactive Gaseous Process and Effluent Monitoring Instrumentation, will be added as follows:

-31 4.1.2 Radioactive Liquid Effluent Instrumentation Applicability: As shown in Table 4.1.2.1 Objective:

To specify the minimum frequency and type of surveillance to be applied to the radioactive liquid instrumentation.

Specification:

A. The setpoints shall be determined in accordance with pro cedures as described in the ODCM and shall be recorded on the release permit.

B. Each radioactive liquid effluent monitoring instrumenta tion channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 4.1.2.1.

C. Auditable records shall be maintained, in accordance with procedures in the ODCM, of all radioactive liquid effluent monitoring instrumentation alarm/trip setpoints. Set points and setpoint calculations shall be available for review to ensure that the limits of Specification 3.15.1 are met.

Basis:

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instru ments are calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

TABLE 4.1.2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVBILLANCE REQUIREMENTS.

CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Auto matic Isolation

a. Liquid Radwaste Effluents Line W*

W R(2)

SA(1)

b. Steam Generator Blowdown Effluent N/A N/A R(2)

SA(1)

Line

2. Flow Rate Monitors

a. Liquid Radwaste Effluent Line D(3)

N/A R

SA

-32 TABLE 4.1.2.1 (Continued)

TABLE NOTATION

• During releases via this pathway.

(1)

The CHANNEL TEST also demonstrates the following:

1. Automatic isolation of this pathway and control room alarm annunciation-occurs when-the instrument indicates measured levels above the alarm/trip setpoint.

2. Local annunciation in the event of a circuit failure.

3. Local annunciation when the instrument indicates a downscale failure.

4. Control room alarm annunciation when the instrument controls are not set in the operate mode.

(2)

For CHANNEL CALIBRATION the channel check source is used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

-33 4.1.3 Radioactive Gaseous Process And Effluent Monitoring Instrumentation Applicability:

As shown in Table 4.1.3.1 Objective:

To specify the minimum frequency and type of surveillance to be applied to the radioactive gaseous monitoring instrumentation.

Specification:

A. The setpoints shall be determined in accordance with procedures as described in the ODCM and shall be recorded on the release permit.

B. Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 4.1.3.1.

C. Auditable records shall be maintained of the calculations made, in accordance with procedures in the ODCM, of all radioactive process and effluent monitoring instrumentation alarm/trip setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Specification 3.16.1 are met.

Basis:

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radio active materials in gaseous effluents during actual or potential releases.

The alarm/trip setpoints for these instruments are calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

0 TABLE 4.1.3.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Stack Monitoring System

a. Gross Activity Monitor W

W R(2)

SA(1)

b. Noble Gas Activity Monitor W

W R(2)

SA(1)

c. Iodine Sampler Cartridge W

N/A N/A N/A

d. Particulate Sampler Filter W

N/A N/A N/A

e. Stack Fan Flow Indication N/A N/A N/A SA

f. Sampler Flow Rate Measuring N/A N/A SA Device

-35 TABLE 4.1.3.1 (Continued)

TABLE NOTATION

• At start of release via this pathway.

(1) The CHANNEL TEST also demonstrates the following:

1. Automatic isolation of this pathway and control room alarm annunciation occurs when the instrument indicates measured levels above the alarm/

trip setpoint.

2. Local annunciation in the event of a circuit failure.

3.

Local annunciation when the instrument indicates a downscale failure.

4.

Control room alarm annunciation when the instrument controls are not set in the operate mode.

(2) For CHANNEL CALIBRATION the channel check source is used.

-36 In Appendix A, Specification 4.5, Radioactive Liquid Waste Release, will be replaced by the following:

4.5 RADIOACTIVE LIQUID EFFLUENTS 4.5.1 Liquid Effluents Concentration Applicability:

At all times Objective:

To verify that discharge of radioactive liquid material to unrestricted areas is maintained below 10CFR 20 limits.

Specification:

A. The concentration of radioactive material at any time in liquid effluents released from the site shall be con tinuously monitored in accordance with Table 3.5.3.1.

B. The liquid effluent continuous monitors having provisions for automatic termination of liquid releases, as listed in Table 3.5.3.1, shall be used to limit the concentration of radioactive material released at any time from the site to unrestricted areas to the values given in Specification 3.15.1.

C. The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.5.1.1.

The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is limited to the values in Specification 3.15.1.

-37 D. Post-release analyses of samples from batch releases.shall be performed in accordance with Table 4.5.1.1.

The results of the post-release analyses shall be used with the calcula tional methods in the ODCM to assure that the concentrations at the point of release are limited to the values in Specifi cation 3.15.1.

E. The radioactivity concentration of liquids discharged from feedwater and steam generator blowdown release points shall be determined by collection and analysis of samples in accordance with Table 4.5.1.1.

The results of the analyses shall be used with. the calculational methods in the ODCM to assure that the concentrations at the point of release are limited to the values in Specification 3.15.1.

F. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1e.

Basis:

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.

-37a TABLE 4.5.1.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Sampling Minimum Type of Activity of Detection Liquid Release Type Frequency Analysis Analysis (LLD)

Frequency (uCi/ml)a P

P A. Batch Waste Re-Each Batch Each Batch Principal Gamma 5 x 10-7b lease Tankse Emittersf 1-131 1 x 10- 6 P

One Batch./M M

Dissolved and 1 x 10-5 Entrained Gases P

H-3 1 x 10-5 Each Batch M

Compositec Gross a 1 x 10-7 P-32 1 x 10-6 P

Each Batch Q

Sr-89, Sr-90 5.x 10-8 Compositec Fe-55 1 x 10-6 B. Feedwater and W

W Principal Gamma 5 x 10 Steam Genera-Grab Sample Composited Emitters tor Blowdown Releases 1-131 1 x 10-6 M

Grab Sample M

Dissolved and 1 x 10-5 Entrained Gases W

Grab Sample D

H-3 1 x 10-5 W

M Grab Sample Composited Gross a 1 x 10-7 P-32 1 x 10-6 W

Grab Sample Q

Sr-89, Sr-90 5 x 10-8 Composited Fe-55 1 x 10-0

-38 TABLE 4.5.1.1 (Continued)

TABLE NOTATION

a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability.

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

4.66 s LLD=

E

• V - 2.22

• Y

• exp(-XAt)

where, LLD is the lower limit of detection as defined above (as pCi per unit mass of volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per transformation)

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 applicable)

A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting

-39 TABLE 4.5.1.1 (Continued)

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

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 (e.g., potassium-40 in milk samples).

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

.b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inversely proportionally to the magnitude of the gamma yield (i.e., 5 x 10-7/I, where I is the photon.abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2.

c.

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.

-40 TABLE 4.5.1.1 (Continued)

d.

To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected routinely in proportion to the rate of flow of the effluent stream.

Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

e.

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

f.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level.

When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semiannual Radioactive Effluent Release Report.

4.5.2 Liquid Effluent Dose Applicability:

At all times Objective:

To verify that doses due to the release of radioactive liquid effluents are as low as is reasonably achievable.

-'41 Specification:

A.- Cumulative dose contributions from liquid effluentsshall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once per 31 days.

B. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1e.

Basis:

This specification is provided to implement the requirements of Section III.A of Appendix I, 10 CFR Part 50.

The dose cal culations in the ODCM implement the requirement in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under estimated.

4.5.3 Liquid Waste Treatment Applicability:

At all times Objective:

To verify the operability and potential use of the liquid radwaste treatment system.

Specification:

A. Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.

B. The liquid radwaste system consisting of the following minimum components shall be demonstrated OPERABLE at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days:

1. 2 Holdup Tanks

2. 1 Holdup Tank Pump

3. 1 Demineralizer

4. Associated Piping and Valving Basis:

The OPERABILITY 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. The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."

This specifica tion implements the requirements of 10 CFR Part 50.36a and design objective 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 guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

Appendix A, Specifications 4.6, Radioactive Gaseous Waste Release, will be replaced by the following:

-J43 4.6 RADIOACTIVE GASEOUS EFFLUENTS 4.6.1 Dose Rate Applicability:

At all times Objective:

To verify the dose rate due to the discharge of radioactive gaseous effluents is maintained within 10 CFR 20 limits.

Specification:

A. The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established in Specification 3.16.1.

B. The noble gas effluent continuous monitors having provisions for the automatic termination of gaseous releases, as listed in Table 3.5.4.1, shall be used to limit offsite doses within the values established in Specification 3.16.1 when monitor setpoint values are exceeded.

C. The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.6.1.1.

D. The dose rate in unrestricted areas, due to radioactive materials other than noble gases released in gaseous ef fluents, shall be determined to be within the required limits by using the results of the sampling and analysis program, specified in Table 4.6.1.1, in performing the calculations of dose rate in unrestricted areas.

-'4 4 E. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1e.

Basis:

This specification is provided to ensure that the dose rate at anytime at the exclusion area boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.

These limits provide reasonabl'e assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to.compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to < 500 mrem/year to the total body or to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the correspond ing thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

TABLE 4.6.1.1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)

Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)a P

P A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emittersf 1 x 10 -4b Tank Grab Sample P

P B. Containment Purge Each Purgec Each Purgec Principal Gamma Emittersf 1 x 10 -4b Grab Sample H-3 1 x 10-b C. Plant Stack Continuouse Wd

-131 1 x 10-12 Charcoal Sample 1-133 1 x 10-10 Continuouse Wd Particulate Principal Gamma Emittersf Sample (1-131, Others) 1 x 10-11 Continuouse M

Gross alpha 1 x 10-11 Composite Particulate Sample Continuouse.

Q SR-89, Sr-90 1 x 10-11 Composite Particulate Sample

TABLE 4.6.1.1 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.5.1.1 of Specification 4.5.1.

b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inversely proportionally to the magnitude of the gamma yield (i.e., 1 x 10-4/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column I.

c. Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.

d. Analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or similar operational ocurrence which could lead to significant increases or decreases in radioiodine releases.

Samplers shall also be changed and analyzed at the intervals in Specifi cations 3.16.1 and 3.16.3.

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.

e. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.16.1, 3.16.2 and 3.16.3.

f. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m,

14 6 Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-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 reportedi Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi annual effluent report.

4.6.2 Dose Noble Gases Applicability:

At all times Objective:

To verify the dose due to noble gases in radioactive gaseous effluents is maintained as low as is reasonably achievable.

Specification:

A. Cumulative dose contributions for the total time period shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once every 31 days.

B. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1e.

Basis:

This specification implements the requirements in Section III.A of Appendix I, 10 CFR Part 50, that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially

underestimated. The ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.

4.6.3 Dose, Radioiodines, Radioactive Material in Particulate Form, and Radionuclides other than Noble Gases Applicability:

At all times Objective:

To verify the dose due to radioiodines, radioactive material in particulate form and radionuclides other than noble gases is maintained as low as is reasonably achievable.

Specification:

A. Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.

B. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1e.

Basis:

This specification implements the requirements in Section III.A of Appendix I, 10 CFR Part 50, 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.

e1

The ODCM equations provided for determining the actual doses are based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

4.6.4 Gaseous Radwaste Treatment Applicability:

At all times Objective:

To verify the operability and potential use of the gaseous radwaste treatment system and the ventilation exhaust treatment system.

Specification:

A. Doses due to gaseous releases to unrestricted areas shall be projected at least once per 31 days.

B. The gaseous radwaste treatment system consisting of the following minimum components shall be demonstrated OPERABLE at least once per 92 days unless the system has been utilized to process radioactive gaseous effluents duriing the previous 92 days:

-49

1. Waste Gas Surge Tank

2. 1 Gas Compressor

3.

2 Waste Gas Decay Tanks

4. Associated Piping and Valving Basis:

The OPERABILITY of the gaseous radwaste treatment system and the ventilation exhaust treatment systems 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 gaseous effluents will be kept "as low as is reasonably achievable."

This specification implements the requirements of 10 CFR Part 50.36a and design objective Section II.D of Appendix I to 10 CFR Part 50.

4.6.5 Gas Storage Tanks Applicability:

At all times Objective:

To verify the quantity of radioactive material contained within the gas storage tanks.

Specification:

The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limit specified in Specification 3.16.5 at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when radioactive materials are being added to the tank.

-50 Basis:

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure."

To Appendix A Specifications 4.17, Dose, and 4.18, Radiological Environmental Monitoring, will be added:

4.17 Dose Applicability:

At all times Objective:

To verify the doses due to liquid and gaseous effluents are maintained as low as is reasonably achievable.

Specification:

A. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifica tions 3.15.2.A, 3.16.2.A and 3.16.3.A and in accordance with the Offsite Dose Calculation Manual (ODCM).

B. Special reports shall be submitted as required under Specification 3.17.

Basis:

This specification is provided to meet the reporting require ments of 40 CFR 190.

-51 O

4.18. RADIOLOGICAL ENVIRONMENTAL MONITORING 4.18.1 Monitoring Program Applicability:

At all times Objectives:

Ensure required actions of the radiological monitoring program are being performed.

Specification:

A. The radiological environmental monitoring samples shall be collected pursuant to Table 3.18.1 from the locations identified on Figures 3.18.1, 3.18.2 and 3.18.3 shall be analyzed pursuant to the requirements of Tables 3.18.1 and 4.18.1.

B. The results of -analyses performed on the radiological environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1d.

Basis:

The radiological monitoring program 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 station operation.

4.18.2 Land Use Census Applicability:

At all times.

Objective:

Perform the land use census to ensure the monitoring program is appropriate for the surrounding areas.

9e*

TABLE 4.18.1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

Drinking Ocean Airborne Water Water Particulate Marine Local Beach Ocean Jack or Gas Animals Crops Kelp Sand Bottom Rabbit Analysis (pCi/1)

(pCi/1)

(pCi/m 3 )

(pCi/g)2 (pCi/g)2 (pCi/g)2 (pCi/g)

(pCi/g)

(pCi/g)

Gross beta 0.5 (0.1)1 0.5

.003 Gross alpha 5.0 (0.3)1 5.0

.003 H-3 200 11 11 10 Sr-90 1

.001

.o4 2.0 Sr-89 3.0 Cs-137 5

6 0.03

.03

.06

.07

.07

.06 1-131 10

.04

.03

.2

.05 (5.0)3 Co-58 0.1

.13

.07 Co-60 0.2

.20

.11 Ag-110m 0.4

.07

.07 Footnotes

1. Solids

2. Dry wt.

3. Thyroid

-52 Specification:

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

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

Basis:

• This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifica tions to the monitoring program are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.e of Appendix I to 10 CFR Part 50.

4.18.3 Interlaboratory Comparison Program Applicability:

At all times Objective:

To ensure laboratory analysis of radiological environmental monitoring samples is correct and accurate.

Specification:

The results of analyses performed as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1d.

Basis:

The requirement for participation in an Interlaboratory Compari son Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive

-53 the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

To Appendix A, Section 6.5.1.6, the following will be added:

j. Review of every unplanned release of radioactive material to the environs; evaluate the event; specify remedial action to prevent recurrence; and document the event description, evaluation, and corrective action and the disposition of the correctiveaction in the plant records.

To Appendix A,, Section 6.5.2.8, the following will be added:

k. 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.

Appendix A, Section 6.8.1, will be revised as follows:

Written procedures and administrative policies shall be established, imple mented and maintained that meet or exceed the requirements and recommendations of Sections 5.2 and 5.3 of ANSI N18.7-1976, Administrative Controls for Nuclear Power Plants; Appendix "A" of USNRC Regulatory Guide 1.33, Rev. 1, Quality Assurance Program Requirements (Operation); Paragraph 2.2.1 of Fire Protection Program Review. BTP APCSB 9.5-1, San Onfore Nuclear Generating Station, Unit 1, March, 1977; and the Offsite Dose Calculation Manual; except as provided in 6.8.2 and 6.8.3 below.

Appendix A, Section 6.9.1, Routine Reports, will be revised as follows:

c. Monthly Operating Report Routine reports of operating statistics and shutdown experience 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, to be submitted by the fifteenth of each month following the calendar month covered by the report.

In addition, any changes to the Offsite Dose Calculation Manual of Specification 6.12 shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective.

d. Annual Radiological Environmental Operating Report Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental 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.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

-55 The annual radiological environmental operating reports shall include summarized and tabulated results in the format of -Table 6.9.1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Quality Assurance Program required by Specification 3.18.3.

e. Semiannual Radioactive Effluent Release Report Routine radioactive effluent release reports covering the operation 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 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 Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

0 TABLE 6 1.

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Docket No.

Location of Facility Reporting Period (County, State)

Medium or Pathway Analysis and Lower Limit All Indicator Location with Highest Number of Sampled Total Number of Locations Annual Mean Control Locations Non-Routine (Unit of of Analyses Detection*

• • Mean (f)

Name, Distance **Mean (f)

• • Mean (f)

Reported Measurement) Performed (LLD)

• • Range

& Direction

• • Range

• • Range Measurements***

Air Parti culates (pCi/m )

416 0.003 0.08 (200/312) Middletown 0.10 (5/52) 0.08 (8/104) 1 (0.05 -

2.0) 5 miles 340 (0.08 -

2.0)

(0.05 -

1.40) 32 0.003 0.05 (4/24)

Smithville 0.08 (2/4)

<LLD 4

Cs (0.03 -

0.13) 2.5 miles 160 (0.03 -

0.13)

Ba 0.003 0.03 (2.24)

Podunk 0.05 (2/4) 0.02 (1/8) 1 1

(0.01 -

0.08).

4.0 miles 270 (0.01 -

0.08)

Sr 40 0.002

<LLD

<LLD 0

Sr 40 0.0003

<LLD

<LLD 0

Fish 8

pCi/kg Cs 80

<LLD

<LLD 90 (1/4) 0 (dry weight)

Cs 80

<LLD

<LLD

<LLD 0

Co 80 120 (3/4)

River Mile 35 See column 4 LLD 0

(90 -

200)

Podunk River Nominal Lower Limit of detection (LLD) as defined in HASL -

300 (Rev. 8/73), pp. D-08-01,02,03.

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f).

Non-routine re ote measurements are defined in Section 5.6.2.

NOE: The exa ple data are provided for illustrative purposes only.

TABLE 6.9.2.1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Particulate Marine Animals Local Crops Analysis (pCi/1) or Gases (pCi/m 3)

(pCi/Kg, wet)

(pCi/Kg, wet)

H-3 3 x 10 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 10 1-131 2

0.9 1 x 1021 Cs-137 50 20 2 x 103 2 x 103

-56 The radioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, with data sum marized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 3.16.1.1) during the report period. All assumptions used in making these assessments (e.g.,

specific activity, exposure time and location) shall be included in these reports.

The radioactive effluent release reports shall include the following in formation for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned release.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21.

In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.

The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).

-57 To Appendix A, Section 6.9.2a., the following events will be added:

10. Occurrence of an unusual or important event that causes a significant environmental impact, that affects potential environmental impact from unit operation, or that has high public or potential public interest concerning environmental impact from unit operation.

(See Specifications 3.15.1 and 3.16.1)

11. Occurrence of radioactive material contained in gaseous holdup tanks in excess of that permitted by the limiting condition for operation established in specification 3.16.5.

To Appendix A, Section 6.9.2.b, the following events will be added:

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

1.

A 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.

6. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9.2.1.when averaged over any calendar quarter sampling period.

(See Specification

-58 3.18.1.B.2).

When more than one of the radionuclides in Table 6.9.2.1 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) limit level (1)

+

limit level (2)

+... > 1.0 When radionuclides other than those in Table 6.9.2.1 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 3.15.2, 3.16.2 and 3.16.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

To Appendix A, Section 6.9.3, the following will be added:

d. Radiological Effluents (Technical Specifications 3.15.2, 3.15.3, 3.16.2,

.3.16.3, 3.16.4 and 3.17).

e. Radiological Environmental Monitoring (Technical Specifications 3.18.1 and 3.18.2).

To Appendix A, the following Sections, 6.12, Offsite Dose Calculation Manual, and 6.13, Major Changes to Radioactive Waste Treatment Systems, will be added:

6.12 OFFSITE DOSE CALCULATION NANUAL (ODCM) 6.12.1 The ODCM describes 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.

-59 6.12.2 Changes to the ODCM are made in the following manner:

1. Changes shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.9.1c 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 without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, 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 determinations; and

c. documentation of the fact that the change has been reviewed and found acceptable by the OSRC.

2. Changes shall become effective upon a date specified and agreed to by the OSRC following their review and acceptance of the change(s).

6.13 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID AND GASEOUS)

Major changes to the radioactive waste systems (liquid and gaseous) are made in the following manner. For the purpose of this specification "major changes" is defined in Section 1.0.

-60

1) The Commission shall be informed of all changes by the inclusion of a suitable discussion of each change in the Semi-annual Radioactive Effluent Release Report for the period in which the changes were made.

The discussion of each change shall contain:

a) a summary of the evaluation that led to the determination that the change could be made (in accordance with 10CFR50.59);

b) sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c) a detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d) an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents from those previously predicted in the license application and amendments thereto; e) an evaluation of the change which shows the expected maximum exposures to an individual in the unrestricted area and to the general population from those previously estimated in the license application and amendments thereto; f) a comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the period in which the changes were made.

-61 g) an estimate of the exposure to plant operating personnel as a result of the change; and h) documentation of the fact that the change was reviewed and found acceptable by the OSRC.

2) The change shall become effective upon review and acceptance by the OSRC.

Appendix B, Technical Specification 3.2, Radiological Environmental Monitoring, will be deleted.

Appendix B, Technical Specification 5.6.1, Routine Reports - Annual, Section 5.6.1.c., Radiological Environmental Monitoring, will be deleted.

Appendix B, Technical Specification 5.6.2, Routine Reports - Semiannual, will be deleted.