Text

Amend 79 to License DPR-13,modifying Tech Specs to Add Radiological Effluent Tech Specs Needed to Implement 10CFR50,App I Requirements
	ML13316A685
Person / Time
Site:	San Onofre
Issue date:	08/27/1984
From:	Paulson W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML13316A684	List: ML13316A683; ML13316A685; ML13316A686;
References
	DPR-13-A-079, TAC-08101 NUDOCS 8409040004
	Download: ML13316A685 (75)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 79 License No. DPR-13

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated

.December 12, 1983 as supplemented March 20, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by

~this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8409040004 840827--

PDR ADOCK 05000206 P

PDR

-2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.

DPR-13 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of January 1, 1985.

FOR THE NUCLEAR REGULATORY COMMISSION Walter A. Paulson, Acting Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 27, 1984

ATTACHMENT TO LICENSE AMENDMENT NO. 79 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A and Appendix B Technical Specifications and Bases by removing the following pages and by inserting the enclosed pages.

The revised pages contain the captioned amendment number and marginal lines indicating the area of change.

APPENDIX A REMOVE INSERT la 1c la*

Id

-33s 33t 33u 33v 33w 33x 39n 39o 39p 39q 39r 39s 39t 39u 39v 39w 39x 39y 39z 39aa 39bb 39cc 39dd 39ee 39ff No changes on this page; renumbered as Id.

-2 REMOVE INSERT 44a (1) 44a(2) 44a(3) 44b 44b 44b(1) 44b(2) 54 54 55 55 55a 55b 55c 56 56 57 57 57a 57b 57c 57d 57e 60w 60x 6 0y 60z 60aa 60bb 60cc 66b 66b 75a 75a 79 79 82 82 82a 82b 82c 85 85 86 86 91a 91b APPENDIX B REMOVE INSERT 3-12 through 3-26 3-12 through 3-26 5-9 5-9 5-10 5-10 5-11 5-11 5-12 5-12 5-13 5-13

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

OFFSITE DOSE CALCULATION MANUAL (00CM)

An OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the current methodology and parameters used in the calculation of offsite dose due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program.

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.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134 and 1-135 actually present. The thyroid dose conversion 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."

VENTILATION 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 particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Features (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

FREQUENCY NOTATION The FREQUENCY NOTATION is specified in Table 1.1.

Amendment N6.

7 9

1c SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

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.

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.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analysis, and formulation determination by which SOLIDIFICATION of radio active wastes from liquid systems is assured.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include nonemployees such as vending machine service men or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional and/or recreational purposes.

Amendment No. e

Residual Heat Removal (RHR) Train A train of components that includes:

one RHR pump aligned with one RHR heat exchanger; one component cooling water pump aligned with the same RHR heat exchanger and with one component cooling water heat exchanger; and one salt water pump aligned with the same component cooling water heat exchanger.

Operational Mode -

Mode An Operational Mode (i.e., Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

TABLE 1.2 OPERATIONAL MODES REACTIVITY

% RATED AVERAGE COOLANT MODE CONDITION, Kf THERMAL POWER*

TEMPERATURE

1. POWER OPERATION O.99

- 5%

1350aF

2. STARTUP 1 0.99 5 5%

350aF

3. HOT STANDBY

<0.99 0

350aF

4. HOT SHUTDOWN 0.95 0

350 aFAT

> 200aF avg 5.- COLD SHUTDOWN 5 0.95 0

5 200*F

6. REFUELING**

<0.95 0

< 140 0 F Excluding decay heat.

Reactor vessel head unbolted or removed and fuel in the vessel.

Amendment No. M,2, 7

-33s 3.5.8 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION Applicability: During releases via this pathway.

Objective:

Monitor and control radioactive liquid effluent releases.

Specification: A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.5.8.1 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 instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.15.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

2. With less than the minimum number of radioactivF liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.5.8.1.

If the inoperable instruments remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. The provisions of Specifications 3.0 and 6.9.2.b(2) are not applicable.

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 methods in the ODCM to ensure that the alarm/trip will occqr prior to exceeding the limits of 10 CFR Part 20.

Amendment No.7 0

33t TABLE 3.5.8.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent Line (R-1218)

(1) 16

b. Steam Generator Blowdown (a)

(1) 17 Effluent Line (R-1216)

c. Turbine Building Sumps Effluent Line (1) 18 (Reheater Pit Sump) (R-2100*)

d. Yard Sump (R-2101*)

(1) 18

e. Component Cooling Water System (b) (R-1217)

(1) 19

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (FE-16, FE-18)

(1) 20

b. Circulating Water Outfall**

c. Steam Generator Blowdown Effluent**

Line New instrumentation -

Conformance with Technical Specifications will have to be determined following installation.

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

(a) Secondary coolant samples and activity analysis performed in accordance with T.S. 4.1, Table 4.1.2.

(b) Closed loop system. Monitor closes vent valve to isolate surge tank.

Amendment No. 7 9

33U TABLE 3.5.8.1 (Continued)

TABLE NOTATION ACTION 16 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:

1. At least two separate samples which can be taken by a single person are analyzed in accordance with Specification 4.5.1.A.,

and;

2. At least two technically qualified persons verify the release rate calculations and discharge valving;,

ACTION 17 With the number of channels OPERABLE less than requiredty the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml;

1.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when.the specific activity of the secondary coolant is < 0.01 uCi/gram DOSE EQUIVALENT 1-131.

ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-'

microcurie/ml.

ACTION 1 9 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, determine if there is leakage from the Component Cooling Water System to the Salt Water Cooling. System.

If leakage exifts sample the Component Cooling Water System to estimate the actfvity being released via the Salt Water Cooling System at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for gross activity (beta or gamma) at lower limit of detection of at least 10-7 microcurie/m.b ACTION 20 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves generated in-situ may be used to estimate flow.

Amendment No. 7 9

33v 3.5.9 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Applicability: During releases via this pathway.

Objective:

Monitor and control radioactive gaseous releases.

Specification: A. The radioactive gaseous process and effluent monitoring instrumentation channel shown in Table 3.5.9.1 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, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

2. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.5.9.1. If the inoperable instruments remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. The provisions of Specifications 3.0 and 6.9.2.b(2) are not applicable.

Basis:

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable,,the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments are calculated in accordance with methods in the 00CM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

Amendment No.7 9

33w TABLE 3.5.9.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM,:

CHANNELS INSTRUMENT OPERABLE ACTION

1. Stack Monitoring System1

a.

Gross Activity Monitor -

(1) 21 Providing Alarm and Automatic Termination of Release.

(R-1214)2

b. Noble Gas Activity Monitor (1) 22 (R1219 or 12123 or 1254*)

c.

Iodine Sampler Cartridge (1) 23 (R1221 or 1254*)

d. Particulate Sampler Filter (1) 23 (R-1211 or 1220)

e.

Stack Fan Flow Indication (R-1254*)

(1) 24

f. Sampler Flow Rate Measuring Device (1) 24

1. Includes the following subsystems:

a)

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

b) Containment Monitoring System.

c) Air Ejector System.

2. Provides for auto-termination of release from the Waste Gas Holdup System.

3. Provides for auto-termination of containment purge.

New instrumentation - Conformance with Technical Specifications will have to be determined following installation.

Amendment No. 7 9

33x TABLE 3.5.9.1 (Continued)

TABLE NOTATION ACTION 21 With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement and Instrument lb inoperable the contents of a waste gas decay tank may be released to the environment provided that prior to initiating the release:

1.

At least two separate samples which can be taken by a single person of the tank's contents are analyzed; and

2.

At least two technically qualified persons verify the release rate calculations and discharge valve lineup.

All other effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 22 With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement and Instrument la inoperable, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.6.1.1.

ACTION 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this

-pathway may continue provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Amendment No. 7 9

39n 3.15 RADIOACTIVE LIOUID EFFLUENTS 3.15.1 Liquid Effluents Concentration Applicability:

At all times.

Objective:

Maintain the concentration of radioactive liquid material released from the site below 10 CFR 20 limits.

Specification: A.

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Colun 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-1 uCi/ml.

B.

Action:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREASexceeding the above limits, without delay restore the concentration to within the above limits.

Basis:

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site toUNRESTRICTED-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 objectives of Appendix I, 1.0 CFR Part -50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population.

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

Publication 2.

Amendment No. 7 9

390 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 a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1-2) shall be limited:

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

2.

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

B. Action:

1. With the calculated dose from the release of

-radioactive materials in liquid effluents exceeding.

any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2.

The provisions of Specification 3.0 are not applicable.

Basis:

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

Specification A implements the guides set forth in Section II.A of Appendix I. Specification 8 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."

Amendment No.

7 o

39p 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.

Specification: A.

The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to the liquid effluent from San Onofre Unit 1, to UNRESTRICTED AREAS (see Figure 5.1-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

B. Action:

With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems 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.

The provisions of Specification 3.0 are not applicable.

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 whed 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 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.

Amendment No. 7 9

39q 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 10 CFR 20 limits.

Specification: A. The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following values:

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

2. The dose rate limitfor 1-131, 1-133, for tritium and for all radionuclides in particulate form with half lives greater than 8 days shall be < 1500 mrem/year to any organ.

B. Action:

With the dose rate(s) exceeding the above limits, without delay restore the release rate to within the above limit(s).

Basis:

This specification is provided to ensure that the dose rate at and beyond the SITE 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, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the exclusion area boundary, to annual average concentrations exceeding the 11mits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For MEMBERS OF THE PUBLIC 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 a MEMBER OF THE PUBLIC 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 a child via the inhalation pathway to

< 1500 mrem/year.

Amendment No. 7 9

39r 3.16.2

Dose, Noble Gases Applicability: At all times.

Objective:

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

Specification A.

The air dose due to noble gases released in gaseous effluents, from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

1. During any calendar quarter: < 5 mrad for gamma radiation and < 10 mrad for beta radiation.

2. During any calendar year: < 10 mrad for gamma.

radiatio, and < 20 mrad for beta radiation.

B. Action:

1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2. The provisions of Specification 3.0 are not applicable.

Basis:

This specification is provided to implement the requirements of Sections II.8 and IV.A of Appendix I, 10 CFR Part 50.

Specification A implements the guides set forth in Section II.8 of Appendix I.

Specification B provides the required operating flexibility and at the same time implements the.guides set forth in Settion-IV.A of Appendix I to assure tha.t the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable.

Amendment No.

39s 3.16.3 Dose, Iodine-131, lodine-133, Tritium and Radionuclides in Particulate Form 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 a MEMBER OF THE PUBLIC from 1-131, I-133, from tritium and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

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

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

B. Action:

1. With the calculated dose from the release of 1-131, 1-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

2. The provisions of Specification 3.0 are not applicable.

Basis:

This specification is provided to implement the requirements of Sections II.C and IV.A-f 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."

Amendment No. 7 9

39t 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 used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.2 mrad for gamma radiation and 0;4 mrad for beta radiation over 31 days.

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 San Onofre Unit 1 to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) would exceed 0.3 mrem to any organ over 31 days.

B.

Action:

1. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification.6.9.3, a Special Report which includes the following information:

a. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reasons for the inoperability.

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

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

2.

The provisions of Specification 3.0 are not applicable.

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, aseous 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 Amendment No. 7 9

39u 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 'Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3.16.5 Gas Storage Tank 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 gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

The provisions of Specification 3.0 are not applicable.

Basis:

The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specificatfon to a quantity that is. less than the quantity which provides assurance that in the event of an uncontrolled release of the tank's -contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 individual at the nearest exclusion area boundary will not exceed 0.5 mrem. This is consistent with Branch Technical Position EtSB 11-5 in NUREG 0800, July 1982.

Amendment No. 7 9

39v 3.16.6 Explosive Gas Mixture Applicability:

At all times.

Objective:

Limit the amount of explosive gases contained in the gas storage tanks.

Specification: A.

The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

B. Action:

1.

With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

2. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.

3.

The provisions of Specification 3.0 are not applicable.

Basis:

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen land oxygen.

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

Amendment No. 7 9

39w 3.17 DOSE Applicability:

At all times.

Objective:

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

Specification:

A.

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity.

and to radiation, from uranium fuel cycle sources shall be limited to < 25 mrem to the total body or any organ (except the thyroid, which shall be limited to < 75 mrem).

B. Action:

1. 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, calculations should be made to determine whether the above limits of Specification 3.17 have been exceeded.

If such is the case, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.3 a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

The Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance-with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted udtil staff action on the request is complete.

2. - The-provisions of Specification 3.0 are not applicable.

Basis.

This specification is provided to meet the reporting requirements of 40 CFR 19.0.

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

Amondment No 7 9

39x 3.18 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.18.1 Monitoring Program Apolicability:

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.

B. Action:

1.

With the radiological environmental monitoring program not being conducted as specified in Table 3.18.1, in lieu of a Licensee Event Report, 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.

2.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 3.18.2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to Specification 6.9.3. When more than one of the radio nuclides in Table 3.18.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1)

+ concentration (2)

+...

> 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.18.2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Speci fications 3.15.2, 3.16.2 and 3.16.3.

This report is not required if the measuredalevel 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.

3..

With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 3.18.1, in lieu of any other report required by Specification 6.9.2.b, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Amendment No.

7 9

39y Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.18.1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring brogram as replacement locations.

4.

The provisions of Specification 3.0 are not applicable.

Basis:

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 a MEMBER OF THE PUBLIC resulting from the station operation.

This monitoring program thereby supplements the radiological effluents 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.

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.

Amendment No. 7 9

39z TABLE 3.18.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and Type and and/or Sample and Sample Locationsa Collection Frequencya Frequency of Analyses

1. AIRBORNE Samples from at least 5 Continuous operation of Radiolodine cartridge.

Radiolodine and locations sampler with sample Analysis at least once Particulates 3 samples from offsite collection as required per 7 days for 1-131.

locations (in different by dust loading but at Particulate sampler.

sectors) of the highest least once per 7 days.d Analyze for gross beta calculated annual average radioactivity >

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ground level D/Q.

following filter change.

Perform gamma isotopicb 1 sample from the vicinity analysis on each sample of a community having the when gross beta activity highest calculated annual is > 10 time the yearly average ground level D/Q.

mean of control samples.

Perform gamma isotopic 1 sample from a control location analysis on composite 15-30 km (10-20 miles) distant (by location) sample at and in the least prevalent least once per 92 days.

wind direction.c

2. DIRECT At least 30 locations including At least once per 92 days.

Gamma dose. At least RADIATIONe an inner ring of stations in once per 92 days.

the general area of the SITE BOUNDARY and an outer ring approximately in the 4 to 5 mile range from the site with a station in each sector of rD each ring.

The balance of the stations are in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.

39aa Exposure Pathway Number of Samples Sampling and Type and and/or Sample and Sample Locations Collection Frequencya Frequency of Analyses

3. WATERBORNE

a. Ocean 4 Locations At least once per month Gamma isotopic analysis and composited quarterly of each monthly sample.

Tritium analysis of composite sample at least once per 92 days.

b. Drinking 2 Locations Monthly at each Gamma Isotopic and location.

tritium analyses of each sample.

c. Sediment 4 Locations At least once per Gamma isotopic analysis from 184 days.

of each sample.

Shoreline

d. Ocean 5 Locations At least once per Gamma isotopic analysis Bottom 184 days.

of each sample.

Sediments

4.

INGESTION

a. Nonmigratory 3 Locations one sample from each Gamma isotopic analysis Marine group (listed below) on edible portions.

Animals will be collected in j

CD L

.a.season, or at least once per 184 days if not seasonal. Groups to be sampled:

0

,1.

Fish-2 adult species such as flatfish, bass, perch or sheepahead.

2. Crustaceae-ouch as crab or lobster.

3.

Mollusks-ouch as limpets, clams or seahares.

39bb Exposure Pathway Number of Samples Sampling and Type and and/or Sample and Sample Locations Collection Frequencya Frequency of Analyses

b. Local Crops 2 Locations Representative vegetables, Gamma isotopic analysis normally 1 leafy and 1 on edible portions semi fleshy collected at annually an 1-131 harvest time.

At least analysis for leafy 2 vegetables collected crops.

semiannually from each location.

TABLE NOTATION

a. Sample locations are indicated in the ODCH.

b. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that-may be attributable to the effluents from the facility.

c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.

d. Canisters for the collection of radiolodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.

e. Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Kor the purpose of this table, a thermolumindscent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

39cc TABLE 3.18.2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATION IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gases Marine Animals Local Corps Analysis (pCi/1)

(pCi/nr3)

(pCi/Kg, wet)

H-3 2 x 104(a)

Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-Nb-95 4 x 102 1-131 2

0.9 1 x 102 Cs-134 30 10 1 x 103 1 x 103 Cs-137 50 20 2 x 103 2 x 103 Ba-La-140 2 x 102 (a) For drinking water samples. This is 40 CFR Part 141 value.

Amendment No.

.1~~~~~~~~~~~~~~~~

9_________________________

39dd 3.18.2 Land Use Census Applicability:

At all times.

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 16 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, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the new locations.

Identify the new locations in the next Semiannual Radioactive Effluent Release Report.

2. With a land use census identifying a location(s) which yields a calculated dose or dose commitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.18.1, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.3, a Special Report which identifies the new locations. The new location shall be added to the radiological environmental monitoring program with 30 days. The sampling location, excluding the control station location, having the lowest 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.

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

Amendment No.

79

39ee

3.

The provisions of Specification 3.0 are not applicable.

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. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used.

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 (25 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consusotion 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.

Specification:

A.

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

B. Action:

.1.

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.

2. The provisions o-f Specification 3.0 are not applicable.

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 the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

Amendment No.

_________________~~~~~

9_______

39ff 3.19 SOLID RADIOACTIVE WASTE Applicability:

At all times.

Objective:

Ensure meeting the requirements for the SOLIDIFICATION and shipment of solid radwaste.

Specification: A.

The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.

B.

Action:

1.

With the provisions of the PROCESS CONTROL PROGRAM not satisfied suspend shipmehts of defectively processed or defectively packaged solid radioactive wastes from the site.

2.

The provisions of Specification 3.0 and 6.9.2b(2) are not applicable.

Basis:

This speci fication implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50.

The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Amendment No.

44a(1) 4.1.2 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION Applicability:

During releases via this pathway.

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 procedures as described in the ODCM.

B. Each radioactive liquid 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 4.1.2.1.

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 methods in 00CM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

Amendment No.

7 9

44a(2)

TABLE 4.1.2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta or Gamma Radioactivity Monitoring Providing Alarm and..

Automatic Isolation

a.

Liquid Radwaste Effluents D.

P R(3) 0(1)

Line (R-1218)

b. Steam Generator Blowdown 0

M R(3)

Q(l)

Effluent Line (R-1216)

c. Turbine Building Sumps D

M R(3)

Q(1)

Effluent Line Reheater Pit Sump (R-2100*)

d. Yard Sump (R-2101*)

0 M

R(3)

Q(1)

e. Component Cooling Water 0

M R(3)

Q(l)

System (R-1217)

2. Flow Rate Monitors Liquid Radwaste Effluent Line D(4)

N/A R

N/A (FE 16 and FE 18)

New instrumentation -

Conformance with Technical Specification will have to be determined following installation.

Amendment No.

7 9

44a(3)

TABLE 4.1.2.1 (Continued)

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

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(Operating plants may substitute previously established calibration procedures for this requirement.)

(4) 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.

Amendment No.

7 9

44b 4.1.3 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION Applicability: During releases via this pathway.

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.

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.

Basis:

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments are calculated in accordance with methods in the 00CM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

Amendment No.

7 g

44b(1)

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 (R-1214)

P P

R(2)

Q(1)

b. Noble Gas Activity Monitor 0

M R(2)

Q(1)

(R-1219, 1212, 1254*)

c. Iodine Sampler Cartridge W

N/A N/A N/A (R-1221, 1254*)

d.

Particulate Sampler Filter W

V/A N/A

...N/A (R-1211, 1220)

e. Stack Fan Flow Indication D

N/A Q

Q (R-1254*)

f. Sampler Flow Rate Measuring 0

N/A R

N/A Device

New instrumentation - Conformance with Technical Specifications will have to be determinedfollowing installation.

Amendment No. 7 9 I

44b(2)

TABLE 4.1.3.1 (Continued)

TABLE NOTATION (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.

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

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NES.

These standards shall permit calibrating the system over-its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(Operating plants may substitute previously established calibration procedures for this requirement.)

Amendment No. 7g

54 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 AREA is maintained below 10 CFR 20 limits.

Specification: A.

Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program of Table 4.5.1.1.

B.

The results of the radioactivity analyses shall be used in accordance with the methods in. the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.15.1.

Basis:

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

Amendment No.

9

55 TABLE 4.5.1.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum' of Detection Sampling Analysis Type of Activity (LLD)

Liquid Release Tve Frequency Frequency Analysis (uC1/ml)a P

P A. Batch Waste Each Batch Each Batch Principal Gamma 5 x 10-7 Release Tanks Emittersc (1). Holdup Tanksb 1-131 1 x 10-b (2) Monitor Tanksb p

One Batch/M M

Dissolved and 1 x 10-5 Entrained Gases (3) Sewage Sludge (Gamma Emitters)

(Offsite Shipment)

.P Each Batch M

H-3 1-x 10-5 Composited Gross Alpha 1 x 10-7 P

Each Batch Q

Sr-89, Sr-90 5 x 8 Composited Fe-55 1 x 10-6 3 x W W

B. Continuous Grab Sample Compositef Principal Gamma 5 x 10-7 Releases Emittersc (1) Steam Generator Blowdown 1-131 1 x 10-6 (2) Reheater Pit M

Sump Grab Sample M

Dissolved and 1 x 10-5 Entrained Gases (3) Yard Drain Sump (Gamma Emitters.)

3 x W M1 Grab Sample Compositef H-3 1 x 10-5 Gross Alpha 1 x 10-7 3 x W Grab Sample Q

Sr-89, Sr-90 5 x 10-8 Compositef Fe-55 1 x 10-6

~.,AMp-nd rn~

n'~.

55a TABLE 4.5.1.1 (Continued)

TABLE NOTATION

a. The LLD is defined, for purposes of these' specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a *realm signal.

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

LLD =

4.66 sb E. V.

2.22 x 100. Y.

exp (-, 4 t)

where, LLD is the "a priori* lower limit of detection as defined above (as

-- microcur-ies.per unit-mass. or volume),

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

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

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable.),

) is the radioactive decay constant for the particular radionuclide, At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting, Typical values of E, V, Y and. At should be used in the calculation.

It should be recognized that the LLD-is defined as an a Priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particuar measurement.

b. 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.

Amendment No.

7 9

55b

c. 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 that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

d. A composite sample is one which results in a specimen that is representative of the liquids released.

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

f. 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.

Amendment No. 7 9

55c 4.5.2 Liquid Effluent Dose Applicabili.ty; At all times.

Objective:

To verify that doses due to the release of radioactive liquid.

effluents are as low as is Ireasonably achievable.

Specification: Cumulative dose contributions fron liquid effluents shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM) at least once per 31 days.

Basis:

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

The dose calculations in the 00CM 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 a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

4.5.3 Liquid Waste Treatment Applicability:

At all times.

Objective:

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

Specification:

Doses due to liquid releases shall be projected at least once per 31 days in accordance with the-ODCM.

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 specification implements the requirements of 10 CFR Part 50.36a and design objective Section II.0 of Appendix I to 10 CFR Part 50.

The specified limits.governirg 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.

Amendment No.

56 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 dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Specification 3.16.1 in accordance with the methods and procedures of the ODCM.

B. The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of Specification 3.16.1 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 4.6.1.1.

Basis:

This specification is provided to ensure that the dose rate at and beyond the SITE 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 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 ill times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to s.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.

Amendment No.

7 9

57 TABLE 4.6.1.1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

.m Lower Limit Minimum of Detection Sampling Analysis Type of-Activity (LLD)

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

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

P.

B. Containment Each Purgec Each Purgec Principal Gamma 1 x 10-4 Purge Grab Emittersb Sample H-3 I.

.1 x 6 C. Plant Stack Mc Mc Principal Gamma 1 x 10-4 Grab Emittersb Sample H-3de 1 x 6 Continuous W9 I-131 1 x0-12 Charcoal Sample Continuousf Wgf Principal Gamma 1 x 10-11 Particulate Emittersb Sample (1-131, Others)

Continuousf M

Gross Alpha 1 x 10-11 Composite.

Particulate Sample Continuous 0

Sr-89, Sr-90 1 x 10-11 Composite Particulate Sample Continuousf Noble Gas Noble Gases 1 x 10-6 Monitor Gross Beta or Gamma

57a TABLE 4.6.1.1 (Continued)

TABLE NOTATION

a.

The LLD is defined, for purposes of these' pecifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% Drobability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD =

4.66 sb

V.

2.22 x 1I Y.

exo (-

At)

Where, LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

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

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

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

K is the radioactive decay constant for the particular radionuclide, bt for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y and At should-be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measuFement system and not as an a posteriori (after the fact) limlt for a particular measurement.

b.

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

Kr-87, Kr-88, Xe-133, Xe-133m, 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 reported. Other peaks which-are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Amendment No. 7 9

57b

c. Sampling and analysis-shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f.

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.

g. Samples shall be changed at least once per 7.days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or. after removal-fr.om sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if (1).analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3;. and (2) the noble gas monitor shows that the effluent activity has not increased more than a factor of 3.

Amendment No.

9

57c 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: Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the 00CM at least once per 31 days.

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 a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The ODCM equations provided for determining the air doses at the SITE BOUNDARY will be based upon the historical average atmospheric conditions.

4.6.3 Dose, Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form Applicability:

At all times:

Objective:

To verify the dose due to IodIne-131,Jodine-133, tritium and radionuclies in particulate form with half-lives greater than 8 days is maintained as low as is reasonably achievable.

Specification: Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the 00CM at least once per 31 days.

Basis:

This specification implements the requirements in Section III.A of Appendix 1. 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 a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The 00CM equations provided for determining the actual doses are based upon the historical average atmospheric conditions.

The release rate specifications for Iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways which are examined in the development of these

57d calculations are:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetationt 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:

Doses dueto gaseous releases from San Onofre Unit 1 shall be projected at least once per 31 days in accordance with the OCM.

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 Tank Applicability:

At all times.

Objective:

To verify tha 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

Basis:

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rea. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.

Amendment No. 7 9 1

57e 4.6.6 Explosive Gas Mixture Applicability: At all times.

Objective:

Limit the amount of explosive gases contained in the gas storage tanks.

Specification: The concentrations of hydrogen and/or oxygen in the waste gas holdup system shall be determined to be within the limits specified in Specification 3.16.6 by analyzing grab samples of the waste gas holdup system contents at the waste gas decay tank inservice daily and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing.

Degassing is defined as the process to reduce reactor coolant system (RCS) dissolved H2 gas concentration in preparation for refueling or for opening the reactor coolant system.

Basis:

This specification is provided to ensure that the concentration of potentially explosive gas mixture contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

Amendment No. 7 9

60w 4.17 DOSE Applicability: At all times.

Objective:

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

Specification:

Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.15.2.A, 3.16.2.A and 3.16.3.A and in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

Basis:

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 resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual 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 MEMBER OF THE PUBLIC for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC 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. If the dose to any MEMBER OF THE PUBLIC is estimdted to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

Amendment No.

7 9

60x 4.18 RADIOLOGICAL ENVIRONMENTAL MONITORING 4.18.1 Monitoring Program Applicability:

At all times.

Objective:

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

Specification:

The radiological environmental monitoring samples shall be collected pursuant to Table 3.18.1 from the locations given in the table and figure in the 00CM and shall be analyzed pursuant to the requirements of Tables 3.18.1 and 4.18.1.

Basis:

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

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling for the environmental exposure pathways.

The detection capabilities required by Table 4.18.1 are state-of-the-art for routine envjronmental measurements in industrial laboratories. It should be recognized that the LLO is defined as a a priori (before the fact) limit representing the capability o7 a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

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.

Amendment No..

9

60y TABLE 4.18.1 MAXIMUM VALUES FOR THE LOWER LIMITS OF OETECTION (LLO)a~c Airborne Particulate Marine Local Water or Gas Animals Crops Sediment Analysis (pCi)/1 (pCi/m3)

(DCi/kg, wet)

(pCi/kg, wet) (pCi/kg, dry) gross beta 4

1 x 10-2 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 7 x 2 60 Cs-134 15 5 x 10-2 130 60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140 60 La-140 15 Amendment No. 7 9

60z TABLE 4.1.8.1 (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 radiochemical separation):

LLD =

4.66 sb E. V.

2.22. Y. exp (-,kAt) where:

LLD is the "a priori* lower limit of detection as defined above (as picocurie per unit mass or volume).

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

E is the counting efficiency (as counts per transformationy.

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

2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide, 6t is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).

The value of so 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).

Typical values of E, V, Y and t shall be used in the calculations.

Amendment No.

7 9

60aa It should be recognized that the LLD is defined as an a priori (before the fact) limit representing capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.*

b.

LLD for drinking water.

c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) NASL Procedures Manual, HASL-300 (revised annually).

(2) Curries, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal.

Chem.

40, 586-93 (3) Hartwell, J. K.,

"Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

Amendment No.

60bb 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.

Specification:

The land use census shall be conducted at -least once per 12 months between the date of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities.

Basis:

This specification is provided to ensure that changes in the use of UNRESTRICTED AREA are identified and that modifications to the monitoring program are made if required by the results of this census. The bestsurvey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used.

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

4.18.3 Interlaboratory Comoarison Program ADDlicabilty:

At all times.

Objective:

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

Specification:

A summary of the results obtained as part of the Interlaboratory Comparison Program and in accordance with the 00CM shall be included 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 the quality assurance program for environmental monitoring in order-to demonstrate that the results are reasonably valid.

Amendment No. 7 9 4

60cc 4.19 SOLID RADIOACTIVE WASTE Applicability:

At all times.

Objective:

Ensure meeting the requirements for the SOLIDIFICATION and shipment of solid radwaste.

Specification:

THE PROCESS CONTROL PROGRAM shall be used-to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

-SOLIDIFICATION of-the batch-may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.1?,

to assure SOLIDIFICATION of subsequent batches of waste.

Basis:

This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50.

The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste PH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Amendment No.

7 9

I

.u

~

D OStP.,

Ni amr 0aaa as vro 1I r

/

l.se Outo fa 1101.

.5t OC(AN 9

e FGURE5.1.

ECUI Am

-EA Ou fl I4 4

FIGURE 5. 1.1 EXCLUSION AREA

75a 6.5.1.14 Recommended changes to the station security program and implementing procedures shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the Chairman of the NARC.

6.5.1.15 Recommended changes to the station emergency plan, and implementing procedures shall be approved by the Station Manager and transmitted to the Manager of Nuclear Operations and to the Chairman of the NARC.

6.5.1.16 The Station Manager shall assure the performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

6.5.1.17 Reports documenting each of the activities performed under Specifications 6.5.1.9 through 6.5.1.16. shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Chairman of the NARC.

6.5.1.18 The Station Manager shall assure the performance of a review by a qualified individual/organization of every uncontrolled or unplanned release of radioactivity to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the NARC.

Amendment No., 6,

79

b. Review and approve recommended changes to the Technical Specifications.

c. Submit proposed changes to the Technical Specifications to the Commission.

d. Maintain management control with respect to nuclear safety.

6.6 DELETED 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.

b. The Safety Limit violation shall be reported to the Commission, the Manager of Nuclear Operations and to the NARC Chairman immediately.

c. A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by-the OSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the NARC and the Manager of Nuclear Operations, within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the.requirements and rec6mmendations of Sections 5.1 and 5.3 and ANSI N18.7-1976, Administrative -Controls of the 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 Onofre Nuclear Generating Station, Unit 1, March 1977; the OFFSITE DOSE CALCULATION MANUAL; the PROCESS CONTROL PROGRAM: and Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21 Revision 1 June 1974 and Regulatory Guide 4.1 Revision 1 April 1975; except as provided in 6.8.2 and 6.8.3 below.

Amendment No. 3Z,)',54, 66, 7 9

82

c. Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, 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 by the report.

d. Annual Radiological Environmental Operating Report*.

Routine radiological environmental operating reports covering the operation of theunit 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 an analysis of trends 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. The reports shall also include the results of land use censuses required by Specification 3.18.2. 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.

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

Amendment No. x 7 9

82a The annual radiological environmental operating reports shall include summarized and taculated results in tne format of Regulatory Guide 4.8, Oecember 1975 of all radiological environmental samples taken during tne report period. In the event that some results are not availaole for inclusion with-the report, the report shall be submitted noting and explain-ing 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; a map for all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlatoratory Comparison Program, required oy Specification 3.18.3.

(Note: Information which may be required by Specifications 3.18.1.8.1, 2, 3.18.J.8.1 and the Basis of 4.18.1 should be included.)

e.

Semiannual Radioactive Effluent Release Reportv 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 eaci-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," Revision 1, June 1974, with data summarized on a quarterly basis following the fonnat of Appendix 8 thereof.

The radioactive effluent release report to be suornitted 60 days after January.1 of each year shall include an annual summary of hourly meteorological data collected over tne previous year. This annual summiry nay oe either in the form of an nour-by-nour listing of wind speed, wind direction, and atmospheric staoility, and precipitation (if measured) on magnetic tape, or in tne A single submittal may be made for a multiple unit station.

The sue.niczal should comoine those sections that are common to all units at tne station; however, for units with separate radwaste systems, the suoinittal snall specify the releases of radioactive material from each unit.

Amendment No. 79

82b form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This same report.shall al.so include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) 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).

The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluent release reports shall include the following information for each type of solid waste.

shipped offsite during the report period:

a.

Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottom),

In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the opti:on of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

Amendment No.

7 9

.4

82c

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent (e.g,, cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to UNRESTRICTED AREAS of radioactive material in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

6.9.2 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.

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

Amendment No. 7 9 1

85 Note:

This item is intended to provide for reporting of potentially generic problems.

(10)

Offsite releases of radioactive materials in liquid and gaseous effluents that exceed the limits of Specification 3.15.1 and 3.16.1.

(11)

Exceeding the limits in Specification 3.16.5 for the storage of radioactive materials in the listed tanks. The written followup report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

b. Thirty Day Written Reports. The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within 30 days of occurrence of the event. The written report shall include, as a minimum, a completed copy of -a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

(1)

Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by

-the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

(2)

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

Note:

Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as'described in items 6.9.2.b.(1) and 6.9.2.b.(2) need not be reported except where test results themselves reveal a degraded mode as described above.

(3)

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundance provided in reactor protection systems or engineered safety feature systems.

Amendment No. )Z, 79

86 (4)

Abnormal degradation of systems other than those specified in item 6.9.2.a.(3) above designed to contain radioactive material resulting from the fission process.

Note:

Scaled 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.

6.9.3 Unique Reporting Requirements The following special reports shall be submitted as required:

a. Inservice Inspection (Technical Specification 4.7).

b. Reactor Vessel Surveillance Program (Technical Specification 4.9).

c. Fire Protection Systems (Technical Specification 3.14).

d. Radiological Effluents (Technical Specifications 3.15.2, 3.15.3, 3.16.2, 3.16.3, 3.1-6.4 and 3.17).

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

The results of required leak tests performed on sealed sources (Technical Specification 4.12) shall be reported annually if the tests reveal the presence of 0.0054'Ci or more of removable contamination.

Amendment No. 31, 38, 7 9

91a 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

6.16.2 Licensee-initiated changes to the PCP:

1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.1.16.

2. Shall become effective upon review and acceptance pursuant to 6.5.1.16.

6.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The 00CM shall be approved by the Commission prior to implementation.

6.17.2 Licensee-initiated changes to the 00CM:

1. Shall be submitted to the Commission in.the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective. This submittal 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 00CM 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 pursuant to 6.5.1.16.

2. Shall become effective upon review and acceptance pursuant to 6.5.1.16.

Amendment No.

7 9 77=7-7-7

91b 6.18 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS*

(Liquid, Gaseous ana solio) 6.18.1 Licensee-initiated major changes to the radioactive waste treatment systems (liquid, gaseous and solid)-:

1.

Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed pursuant to 6.5.1.16. 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 10 CFR 50.59;

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 and/or quantity of solid waste that differ from those previously predicted in the licensee 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 that.differ from those previously estimated in the licensee application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

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 pursuant to 6.5.1.16.

2.

Shall become effective upon review and acceptance pursuant to 6.5.1.16.

Licensees may choose to submit the information called for in this Specification as part of the annual FSAR update.

Amendment No. 7 9

TABLE OF CONTNTS (Cont't) 3.2 Radiological-Environmental Monitoring * * * *

3_12 Deleted 4.0 SECIAL SURVEILLANCE AND STUDY ACTTVITIES.

4-1 4.1 Chlorine (Deleted) 4.2 Fish Impingement (Deleted) 4.3 Encrainment (Deleted) 5.0 A.DMINISTRATTVE CONTROLS.

5-1 5.1 Responsibility..

5-1 5.2 Organization 5-1 5.3 Review and Audit 5-1 5.4 Action to be Taken if a Limiting Conditipn for Operation is Exceeded (Deletedl.

5 -7c 5.5 Procedures 5 - 7 c 5.6 Station Reporting Requirements.

- 5.6.1 Routine Reports-Annual 5-8 5.6.2 Routine Reports-Semiannual (pe1eted).

5-11 5.6.3 Non-Routine Reports.

5-13 5.6.4 Changes.

5-14b 5.7 Records Retention 5-14 b 5.8 Special Requirements 5-15 5.8.1 Intake System.........*

5-15 5.8.2 Discharge System 5-17 5.8.3 Chemical Effluents (Dletedj......

5-17 5.8.4 Land Management 5-18 ii Amendment No. Z7,

}8, 7

3.2 Radiological Environmental Monitoring (DELETED)

Pages 3-12 through 3-26 Amendment No.

7 3

c. Radiological Environmental Monitoring (DELETED) 5-9 Amendment No.

,f.,3g

______________7_9 (DELETED) 5-10 Amendment No. 79

5.6.2 Routine Reports -

Semiannual (DELETED) 5-11 Amendment,f,

,,)79 77 7--

7 7

l7 t

(DELETED) 5-12 Amendment No.

7 9

(DELETED) 5.6.3 Non-Routine Reports

a. 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and confirmed by telegraph, mailgram, or facsimile transmission.to the Regional Administrator or his designee, no later than the first working day following the event. A written followup report shall be submitted to the Regional Administrator (with copy to the Director, Office of Nuclear Reactor Regulation) within two weeks of the event.

5-13 Amendment No. ;,, 7 9

v t e Letter Sequence Other
TAC:08101, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Approval, Approval Other: ML13310B613, ML13310B616, ML13316A685, ML13324A441, ML13324A447, ML13324A449
MONTHYEAR1984-04-18 [Table View]

ML13316A685

Text

Attachment:

Navigation menu

Search