ML13331A800

Revised Proposed Change 146 to Tech Specs,Making Minor Changes to Radiological Effluent Tech Specs & Deleting Remaining Portion of ETS Contained in App B

ML13331A800
Person / Time
Site:	San Onofre
Issue date:	04/10/1985
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13331A798	List: ML13331A796 ML13331A800
References
TAC-56339, NUDOCS 8504120133
Download: ML13331A800 (32)

Text

3. This license shall be deemed to contain and is subject to the conditions of specified in the following Commission regulations (Title 10, CFR, Chapter 1):

Part 20, Sections 50.54 and 50.59 of Part 50, Section 70.32 of Part 70, Section 40.41 of Part 40 and Section 30.34 of Part 30; is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level Edison is authorized to operate the reactor at steady state power levels up to a maximum of 1347 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in A e dix A s

revised through Amendment No. 81, are here Wineotrk ed in the 81 license.

Southern California Edison Company shall operate the 10/16/81 facility in accordance with the Technical Specifications.

C. Fuel Shipments shall not be resumed (except during cold shutdown condition of the reactor) until the modifications described in the licensee's March 21, 1975 report entitled "Spend Fuel Shipping Cask Handling, San Onofre Nuclear Generation Station, Unit 1," and the 18 initial turbine deck load bearing test and visual inspection have been 1/15/76 satisfactorily completed.

D. The facility may be modified by implementing the "Sphere Enclosure Project:

as described in Amendment 52 to the Final Safety Analysis for the San Onofre Nuclear Generating Station, Unit 1, submitted December 3, 1975; Supplement to the Sphere Enclosure Project Report, 20 submitted March 1, 1976; Second Supplement to the Sphere Enclosure 4/2/77 Report submitted March 25, 1978; additional information submitted by letter dated March 25, 1976 (withheld from public disclosure pursuant to 10 CFR Part 2, Section 2.790(d)).

E. Steam Generator Inspections Southern California Edison shall bring the reactor to a cold shutdown condition to perform an inspection of the steam generators within six equivalent months of operation from the start of operation from the 80 backfitting outage that commenced on February 21, 1982. The 9/4/84 inspection program shall be submitted to the Commission at least 45 days prior to the scheduled shutdown. Commission approval shall be obtained before resuming power operation following this inspection.

F.. Deleted 37 10/31/7; 8504120133 850410 PDR ADOCK 05000206 P

PDR 3

Revised:

10/22/84

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 instrumenta tion 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 86 release of radioactive liquid effluents monitored by 1/1/85 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 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. 3, 3.0. 4, 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 occur prior to exceeding the limits of 10 CFR Part 20.

3-66 Revised:

01/01/85

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 Slowdown (a)

(1) 17 Effluent Line (R-1216)

c.

Turbine Building Sumps Effl ent Line (1) 18 (Reheater Pit Sump) (R-210 ).

d.

Yard Sump (R-210)J (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 Slowdown Effluent*?

Line

$7* 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

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 channels 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 instrumenta-86 tion channels OPERABLE, take the ACTION shown in 1/1/85 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 3.0.3, 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 ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

3-69 Revised:

01/01/85

g 0

33w TABLE 3.5.9.1 RADIOACTIVE SASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Stack Monitoring System1

a.

Gross Activity Monitor -

(1) 21

b. Noble s Activity Monitor (1) 22 (R121Ar 12123 or 1254*)

c.

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

d. Particulate Sampler Filte (1) 23 (R-1211 or 122 o

/25YV4)

e.

Stack Fan Flow Indication (R-1254*)

(1) 2-4

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.

Does not perform any isolation function.

Does not provide control room alarm annunciation when the instrument controls are set in j

Athe mnot operatee modeN Amendment No.

'79

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 vaste 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 flourate is estimated at least once per X hours.

Amendment No. 7 9

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 5.1-1) shall be limited:

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

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

B.

Action:

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding 86 any of the above limits, in lieu of a Licensee 1/1/85 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 Specifications3.0.3 and 3.0.4 are not applicable.

Basis:

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

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

3-106 Revised:

01/01/85

3.15.3 LIQUID WASTE TREATMENT Applicability:

At all times.

Objective:

Maintain radioactive releases from the site as low as is reasonably achieveable 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:

86 1/1/85 Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reason for inoperability.

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

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

the Ls3iosof Specifications and are 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 10CFR Part 50.36a and -the'design objective given in Section II.0 of Appendix I to 10CFR Part 50.

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

3-107 Revised:

01/01/85

3.16.2 DOSE, NOBLE GASES APPLICABILITY:

At all times.

OBJECTIVE:

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

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 radiation 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 86 days, pursuant to Specification 6.9.3, a Special 1/1/85 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 specifications are not applicable.

BASIS:

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

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

3-109 Revised:

01/01/85

3.16.3

DOSE, IODINE-131, Iodine-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM APPLICABILITY:

At all times.

OBJECTIVE:

Maintain the dose due to radiotodines, radioactive materials 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, 1-133, from tritium and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from San Onofre Unit I 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, 36 1-133, tritium and radionuclides in particulate 1/1/85 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 Specifications a

3 are not applicable.

BASIS:

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

Specification A is the guide set forth in Section II.C of Appendix I. Specification B provides the required operating.

flexibility and at the same.time implements the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

3-110 Revised:

01/01/85

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 EXRAUST 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 I 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 86 treatment and in excess of the above limits, in 1/1/85 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 Specifications a

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 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 3-111 Revised:

01/01/85

Speci fcation implements the requirements of 10CFR Part 86 50.36a, and the design objective given in Section II.D of 1/1/85 Appendix I to 10CFR 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, 10CFR Part 50, for gaseous effluents.

Typo aevision:

2/12/85 3-112 Revised:

01/01/85

3.16.5 GAS STORAGE TANK APPLICABILITY:

At all times.

OBJECTIVE:

Limit the amout 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:

O.ith the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

86 T.

he provisions of Specification 1/185 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 Specification 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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.

3-113 Revised: 01/01/85

1

<0 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

86

2. With the concentration of oxygen in the waste gas 1/1/85 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 3.0.3 and 3.0.4 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 and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10CFR Part 50.

3-114 Revised:

01/01/85

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,-.

86 to prevent recurrence of exceeding the above limits 1/1/85 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 until staff action on the request is complete.

3-115 Revised:

01/01/85

00

2. The provisions of Specification 3.

ad3.0.4 are not applicable.

86 1/1/85 BASIS:

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

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

3-116 Revised:

01/01/85

3.18 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.18.1 MONITORING PROGRAM Applicability:

At all times.

Objective:

Monitor exposure pathways for radiation and radioactive material.

Specification:

A.

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

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 86 plant effluents in an environmental sampling medium 1/1/85 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 radionuclides 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 effuents, 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 Specifications 3.15.2, 3.16.2 and 3.16.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

3-117 Revised:

01/01/85

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 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 86 deleted from those required by Table 3.18.1, 1/1/85 provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

4.

The provisions of Specification 3.0.3 and 3.0.4 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.

3-118 Revised:

01/01/85

3.18.2 LAND USE CENSUS APPLICABILITY:

At all times.

OBJECTIVE:

Monitor the UNRESTRICTED AREAS 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 the 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 86 30.days, pursuant to Specification 6.9.3, a Special 1/1/85 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 within 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 the SITE BOUNDARY in the direction section with the highest D/Q in lieu of the garden census.

3-123 Revised: 01/01/85

3. The provisions of Specifications 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 86 from the door-to-door, aerial or consulting with local 1/1/85 agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR 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 consumption by a child. To determine this minimum garden size, the following assumptions were used, (1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,

similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/square meter.

3-124 Revised:

01/01/85

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 Operatine Reoort.

86 1/1/85

2.

s of Specifications 1..53,3.

Lad.6.92b(2)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.

3-125 Revised:

01/01/85

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:

86

1. With the provisions of the PROCESS CONTROL PROGRAM 1/1/85 not satisfied suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

2. The provisions of Specifications3.3an304 are not applicable.

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.

3-126 Revised:

01/01/85

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 Gamna Radioactivity Monitoring Providing Alarm and.

Automatic Isolation

a.

Liquid Radwaste Effluents D.

P R(3)

Q(1)

Line (R-1218)

b. Steam Generator Blowdown 0

M R(3)

Q(l)

Effluent Line (R-1216)

c. Turbine Building Sumps 0

M R(3)

Q(l)

Effluent Line Reheater Pit Sump (R-2100*)

d..

Yard Sump (R-2101*)

0 N

R(3)

Q(1)

e.

Component Cooling Water 0

M R(3)

Q(1)

System (R-1217)

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

N/A R

N/A (FE 16 and FE 18)

Does not provide control room alarm annunciation when the instrument controls are set in the"not operate"mode.

Amendment No.

7 9

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-121 0

R(2)

Q

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 Sa ter W

N./A N/A

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

!ff,/r)

e.

Stack Fan Flow Indication D

N/A Q

Q (R-1254*)

f.

Sampler Flow Rate Measuring 0

N/A R

N/A Device Does not perform any isolation function. Does not provide control room alarm annunciation when the instrument controls are set in the "not operate" mode.

Amendment No. 7 9

TABLE 4.5.1.1 RADIOACTIVE LIQUTO WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit MinImumr of Detection Sampling Analysis Type of Activity (LLD)

Liquld Release Type Frequency Frequency Analysis (uCI/ml)a P

P A. Batch Waste Each Batch Each latch Principal Gamma 5 x 10-7 Release Tanks EmittersC (1) Holdup Tanksb 1-131 1 x 10-6 (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 x10-s Composited Gross Alpha 1 x 10-7 P

Each Batch Q

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

B. Continuou 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 M

f 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 Amendment No.

7 9

57 TABLE 4.6.1.1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

.ini-

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

Gaseous Release Type Frequency Freouency 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, Samp 1 e

H-3 I

x 6 C. Plant Stack MC Ho Principal Gamma I x 10-4 Grab Emittersb Sample H-d,e 1 x 10-6 Continuousf W9 1-131 1 x 10-12 Charcoal Sample Continuousf WO Principal Gamma 1 x 10-11 Particulate Enittersb Sample (1-131, Others)

Continuousf M

Gross Alpha 1 x 10-11 Composite Particulate Sample Continuousf 0

Sr-89, Sr-90 1 x 10-11 Comoosite Particulate Sample Continuousf Noble Gas Noble Gases 1 x 10-6 Monitor Gross Beta or Gamma Amendment No. 7 9

6.5.2 NUCLEAR AUDIT AND REVIEW COMMITTEE (NARC)

FUNCTION 6.5.2.1 The NARC provides independent review and audit of desi nated activities in the area of nuclear safet 22 and environmental impact 4/18/75 COMPOSITION 6.5.2.2 The NARC shall be composed of the:

Manager of Engineering Design Manager of Environmental Affairs Manager of Nuclear Engineering, Safety & Licensing 59 Manager, Quality Assurance 5/7/81 Manager of Nuclear Operations Manager, Nuclear Engineering & Safety Manager, Biological Systems Research and Development San Diego Gas & Electric Representative Chairmanship shall be designated by the Nuclear Control Board.

ALTERNATES 6.5.2.3 Alternate members shall be appointed in writing by the NARC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in NARC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NARC chairman.

22 4/18/75 MEETING FREQUENCY 6.5.2.5 The NARC shall meet at least once per six months.

QUOR M 6.5.2.6 A quorum of NARC shall consist of the Chairman or his designated alternate and four members, including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

6-12 Revised:

2/2/83

(3)

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

(4)

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

Note:

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

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

a.

Inservice Inspection (Technical Specification 4.7) 1/17/76

b. Reactor Vessel Surveillance Program (Technical Specification 4.9)

c. Fire Protection Systems (Technical Specification 3.14).

40 3/8/78

d. Radiological Effluents (Technical Specifications 3.15.2, 3.15.3, 3.16.2, 3.16.3, 3.16.4 and 3.17).

83 1 1/2/84

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

f. Reports of inoperability of Radiation Monitoring Instrumentation as required by Technical Specification 3.5.10.

el',g.

Environmental Protection (Technical Specification 6.19)

The results of required leak tests performed on sealed sources (Technical Specification 4.12) shall be reported annually if the 26 tests reveal the presence of 0.005p Ci or moreof removable 1/17/76 contamination.

6-26 Revised:

3/21/78

6.19 ENVIRONMENTAL PROTECTION FACILITY DESIGN AND OPERATION 6.19.1 This section contains a description of facility design features and operating practices which, if changed, could have a significant effect on environmental impact. Any significant change in facility design features or operating practices described here must be reported to the NRC in accordance with the provisions of Section 6.19.2.a prior to the change.

a. Intake System The circulating water system, under normal operating conditions, draws water from the ocean at a point approximately 3,200 feet offshore. The ocean bottom at this point is approximately 27 feet below mean lower low-water level.

The intake structure rests on a foundation located 33 feet beneath the ocean bottom and rises vertically to a point 10 1/2 feet above the ocean floor. The inside horizontal dimensions of the intake structure are 16 to 21 feet. A velocity cap, 1-foot thick, rests on eight columns above the top of the intake structure. The top surface of the velocity cap is 15 1/2 feet above the ocean bottom and 11 1/2 feet below mean lower low-water.

A 12-foot ID reinforced concrete conduit is connected horizontally to the shoreward side of the intake structure.

This conduit is buried beneath the ocean bottom, with a minimum of 4 feet of sand cover over its top and 4 feet of rock cover surrounding the intake structure.

All sand cover was placed so as to approximate the local ocean bottom profile.

Water entering the top of the intake structure is accelerated to a design velocity of about 2.5 feet per second and directed into a 12-foot ID reinforced concrete conduit. As the water enters the concrete conduit from the structure, it is accelerated to a design velocity of 6.9 feet per second. The circulating water system is designed to deliver 350,000 gpm at this velocity.

The offshore system joins the onshore portion of the circulating water system at the screenwell.

The screenwell is located just inside the seawall on the Station property.

Cooling water entering the onshore system passes, through a coarse bar screen, through finer traveling screens, and proceeds to two circulating water pumps designed to operate at 175,000 gpm. Water entering the screenwell structure is decelerated so that the approach velocity at the screens is approximately 2.0 feet per second.

The circulating water system uses three methods of handling the marine growth and debris associated with the flow of seawater through the plant condensers.

These are heat treating, bar and traveling screens, and chlorination.

Heat treatment is used for incrustation control.

This method consists of reversing the flow in the intake conduit and adjusting the temperature of the water to approximately 100OF and discharging through the intake conduit.

This is accomplished by recirculating a portion of the condenser discharge back through the condenser. Cross-connections between intake and outfall conduits are provided to create the reversal of flow necessary for the treatment of the conduits. Normally only the intake conduit is treated. The water temperature in the outlet conduit can be raised for treatment when necessary. The sudden temperature increase of the cooling water causes incrustations growing in the circulating water system to expire, relax their hold, and be flushed out of the system.

Traveling and bar screens are provided to remove marine growth and debris from the seawater passing through the screenwell.

The materials removed from the seawater are marine growth, shells, fish, driftwood, and other debris present in the ocean.

For chlorination, sufficient sodium hypochlorite is injected into the circulating water upstream of the circulating water pumps three times a day for each condenser half to eliminate slime-forming organisms on condenser internal surfaces.

The traveling screens and bar screens are placed in series, perpendicular to the flow. The screens are cleaned automatically, with the frequency of cleaning being dependent on the rate of material buildup on the screens.

The bar screens are cleaned by a traveling mechanical rake that deposits accumulated debris, by means of a seawater jet spray washing process, into sluiceways for removal.

The traveling screens are motor driven, and are capable of rotating as a unit in continuous sequence when activated by pressure differential due to trash buildup. The debris picked up by the traveling screens is also deposited in a sluiceway by means of a seawater jet spray.

b. Discharge System Under normal operating conditions, the heated cooling water leaves the condenser and is discharged to the ocean through a 12-foot ID 2,600-foot-long concrete conduit. A single point discharge is effected through a discharge structure located in 24 feet of water. The dimension of the structure is the same as the intake; however, there is no velocity cap.

The top of the discharge structure is about 11.5 feet below mean lower low-water.

A 12-foot ID reinforced concrete conduit is connected horizontally to the shoreward side of the discharge structure. This conduit is burled beneath the ocean bottom, with a minimum of 4 feet of sand cover over its top and 4 feet of rock surrounding the discharge structure. All sand and rock cover was placed so as to approximate the local ocean bottom profile.

The water travels through the discharge conduit with a design velocity of 6.9 feet per second and exits with a vertical velocity of about 2.5 feet per second. The vertical orientation creates a single orifice jet diffuser which entrains surroundng cooler water and assists in rapid diminution of the discharge temperature.

About seven minutes is required for water to travel from the condensers to the end of the discharge.

c. Land Management The facility occupies about 16 acres of the 84 acre site.

No use of herbicides is practiced to manage vegetation along the transmission line except in isolated cases to meet property owners, requests or permit stipulations from public agencies. Standard erosion control measures are used to minimize erosion at the facility, at tower sites, and along access roads.

REPORTS 6.19.2 The following reports shall be submitted pursuant to Specification 6.9.3g, with a copy to the Director, Office of Nuclear Reactor Regulation.

a. A report shall be made to the NRC prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 6.19.1 if the change would have a significant adverse effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.

b. Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to station operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report within 30 days.

No routine monitoring programs are required to implement this condition.

The written report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.

Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection. The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.

The following are examples of unusual or important events:

excessive bird impaction events; onsite plant or animal disease outbreaks; mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973; unusual fish kills; increase in nuisance organisms or conditions; and unanticipated or emergency discharge of waste water or chemical substances.

c. Reporting Related to the NPDES Permits and State Certifications Violations of the NPDES Permit or State certification (pursuant to Section 401 of the Clean Water Act) shall be reported to the NRC by submittal of copies of the reports required by the NPDES Permit or certification.

The licensee shall also provide the NRC with a copy of the results of the following studies at the same time they are submitted to the permitting agency:

Section 316(b)

Demonstration Study Changes and additions to the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change is approved. If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

The NRC shall be notified of changes to the effective NPDES Permit proposed by the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the NPDES Permit at the same time the application is submitted to the permitting agency.

LAB:3821F