ML13316A849

Amend 90 to License DPR-13,modifying Portions of Radiological Effluent Tech Specs,Updating Former Section 5.8 of ETS & Redesignating as Section 6.19 of App a Tech Specs & Deleting Remaining Part of App B Tech Specs

ML13316A849
Person / Time
Site:	San Onofre
Issue date:	08/05/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML13316A848	List: ML13316A847 ML13316A849 ML13316A851
References
DPR-13-A-090, TAC-56339 NUDOCS 8508090335
Download: ML13316A849 (34)

Text

REGOj 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 ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 90 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 13, 1984, as supplemented January 16, 1985 and revised April 10, 1985, 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.

856090 33 50805 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 Appendix A, as revised through Amendment No. 90, 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 the date of its issuance.

FOR T NU LEAR REGULATOR COM SSION John

. Zwolinski, Chief Operat ng Reactors Branch #5 Divisi of Licensing

Attachment:

Changes to License No. DPR-13 and the Technical Specifications Date of Issuance: August 5, 1985

ATTACHMENT TO LICENSE AMENDMENT NO.90 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206

1. Revise License DPR-13 by removing page 3 and inserting the enclosed page 3.

2. Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT Table of Contents i - iv 33s 33s 33t 33t 33v 33v 33w 33w 33x 33x 39o 39o 39p 39p 39r 39r 39s 39s 39t 39t 39u 39u 39v 39v 39w 39w 39y 39y 39ee 33ee 39ff 39ff 44a(2) 44a(2) 44b(1) 44b(1) 55 55 57 57 75b 75b 86 86 92 93 94 95

3. Delete Appendix B Technical Specifications in their entirety.

-3

3. This license shall be deemed to contain and is subject to the conditions 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 Appendix A, as revised through Amendment No.

, are hereby incorporated in the license. Southern California Edison Company shall operate the 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 "Spent Fuel Shipping Cask Handling, San Onofre Nuclear Generating Station, Unit 1", and the initial turbine deck load bearing test and visual inspection have been satisfactorily completed. [Amd. No. 18, 1-15-76]

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;

[Amd. No. 20, 4-2-76]

Supplement to the Sphere Enclosure Project Report, submitted March 1, 1976; Second Supplement to the Sphere Enclosure Report, submitted March 25, 1976; additional information submitted by letter dated March 25, 1976, (withheld from public disclosure pursuant to 10 CFR Part 2, Section 2.790(d).

[Amd. No. 20, 4-2-76]

E. Steam Generator Inspections During the refueling outage scheduled to begin no later than November 30, 1985, Southern California Edison shall perform an inspection of the steam generators. The 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. [Amd. No. 89, 6-5-85]

[F.(1) and F.(2) License Conditions relating to steam generator] [Deleted per Amd. No. 37, 10-31-78]

Amendment No. go

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS Table of Contents Page SECTION 1 INTRODUCTION 1.0 DEFINITIONS.......

1 SECTION 2 SAFETY STANDARDS 2.1 REACTOR CORE.

2 Limiting Combination of Power, Pressure and Temperature.....

2 Maximum Safety System Settings.........

2 SECTION 3 LIMITING CONDITIONS FOR OPERATION........

7 3.1 REACTOR COOLANT SYSTEM 8

3.1.1 Maximum Reactor Coolant Activity...........

8 3.1.2 Operational Components................

10 3.1.3 Combined Heatup, Cooldown, and Pressure Limitations 12 3.1.4 Leakage.

17 3.1.5 Pressurizer Relief Valves............

18a 3.1.6 Pressurizer 18b 3.1.7 Reactor Coolant System Vents....

18c 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM.........

.....19 3.3 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS....

21 3.3.1 Operating Status...................

21 3.3.2 Shutdown Status 23 3.3.3 Minimum Water Volume and Boron Concentration in the Refueling Water Storage Tank.

25 3.3.4 Primary Coolant System Pressure Isolation Valves..

25a 3.4 TURBINE CYCLE 3.4.1 Operating Status...................

26 3.4.2 Maximum Secondary Coolant Activity..........

27 3.4.3 Auxiliary Feedwater System..............

27a 3.4.4 Auxiliary Feedwater Storage Tank...........

27b 3.5 INSTPUMFNTATION AND CONTROL..............

28 3.5.1 Operational Safety Instrumentation....

28 3.5.2 Control Group Insertion Limits............

31 i

Amendment No. 90

Pa ge 3.5.3 Control and Shutdown Rod Misalignment 33b 3.5.4 Rod Position Indicating System............

33q 3.5.5 Containment Isolation Instrumentation 33j 3.5.6 Accident Monitoring Instrumentation.........

33n 3.5.7 Auxiliary Feedwater Instrumentation.........

33p 3.5.8 Radioactive Liquid Effluent Instrumentation.....

33s 3.5.9 Radioactive Gaseous Process and Effluent Monitoring Instrumentation........

33v 3.5.10 Radiation Monitoring Instrumentation..

33y 3.6 CONTAINMENT.........................

34 3.7 AUXILIARY ELECTRICAL SUPPLY...........

36 3.8 FUEL LOADING AND REFUELING 38 3.9 CORE AVERAGE BURNUP...

39 3.10 INCORE INSTRUMENTATION.

39a 3.11 CONTINUOUS POWER DISTRIBUTION MONITORING 39c 3.12 CONTROL ROOM EMERGENCY AIR TREATMENT SYSTEM.

39e 3.13 SHOCK SUPPRESSORS (SNUBBERS) OPERABILITY..........

390 3.14 FIRE PROTECTION SYSTEMS OPERABILITY.............

39i 3.15 RADIOACTIVE LIQUID EFFLUENTS....

39n 3.16 RADIOACTIVE GASEOUS EFFLUENTS................

39q 3.17 DOSE 39w 3.18 RADIOLOGICAL ENVIRONMENTAL MONITORING............

39x 3.19 SOLID RADIOACTIVE WASTE 39ff SECTION 4 SURVEILLANCE REOUIREMENTS 40 4.1 OPERATIONAL SAFETY ITEMS..................

40b 4.2 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEM 45 4.3 CONTAINMENT SYSTEMS 47 4.4 EMERGENCY P0EP SYSTEM PERIODIC TESTING.....

52 ii Amendment No. 90

4.5 RADIOACTIVE LIQUID EFFLUENTS................

54

.6 RADIOACTIVE GASEOUS EFFLUENTS................56 4.7 INSERVICE INSPECTION REQUIREMENTS...............

58 4.8 REACTIVITY ANOMALIES....................

60 4.9 REACTOR VESSEL SURVEILLANCE PROGRAM 60-A 4.10 AUGMENTED INSERVICE INSPECTION OF HIGH ENERGY LINES OUTSIDE CONTAINMENT 60-8 4.11 CONTROL ROOM EMERGENCY AIR TREATMENT SYSTEM 60e 4.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 60-G 4.13 TURBINE DECK LOAD BEARING TEST AND VISUAL INSPECTION.

60-H 4.14 SHOCK SUPPRESSORS (SNUBBERS) SURVEILLANCE 60-I 4.15 FIRE PROTECTION SYSTEMS SURVEILLANCE............

60-L 4.16 INSERVICE INSPECTION OF STEAM GENERATOR TUBING.......

60-0 4.17 DOSE 60w 4.18 RADIOLOGICAL ENVIRONMENTAL MONITORING 60x 4.19 SOLID RADIOACTIVE WASTE......

60cc SECTION 5 DESIGN FEATURES 5.1 SITE DESCRIPTION....

61 5.2 CONTAINMENT..

62 5.3 REACTOR 65 5.4 AUXILIARY EQUIPMENT..

67 SECTION 6 ADMINISTRATIVE CONTROLS..................

68 6.1 RESPONSIBILITY...

68 6.2 ORGANIZATION...

68 6.3 UNIT STAFF QUALIFICATIONS 72b iii Amendment No. 90

Paqe 6.4 TRAINING 72b 6.5 REVIEW AND AUDIT......................

73 6.6 DELETED 6.7 SAFETY LIMIT VIOLATION.....

79 6.8 PROCEDURES.......

79 6.9 REPORTING REQUIREMENTS...................

80 6.10 RECORD RETENTION.

.....87 6.11 RADIATION PROTECTION PROGRAM.

....89 6.12 ENVIRONMENTAL QUALIFICATION.

.......91 6.13 SYSTEMS INTEGRITY.

.....91 6.14 IODINE MONITORING............

91 6.15 BACKUP METHOD FOR DETERMINING SURCOOLING MARGIN.....

91 6.16 PROCESS CONTROL PROGRAM.

91a 6.17 OFFSITE DOSE CALCULATION MANUAL.

....91a 6.18 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS.

91b 6.19 ENVIRONMENTAL MONITORING..............

.....92 iv Amendment No.90

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 3.0.3, 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 occyr prior to exceeding the limits of 10 CFR Part 20.

Amendment No. 14r 90

33t TABLE 3.5.8.1 RADIOACTIVE LIQUID 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 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.Xe 90

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 3.0.3, 3.0.4, 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.

Amendment No.74, 90

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 Providina Alarm 2

(R-1214 or (R-1219., 1220 and 1221))

b. Noble Gas Activity Monitor (1) 22 (R12192or 12123 or 1254*)

C.

Iod ne Sampler Cartridge (1) 23 (R1221 or 1254*)

d. Particulate Sampler Filter (1) 23 (R-1211 or 1220 or 1254*)

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.

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. 19',90

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 <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 flowrate is estimated at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Amendment No.

90

39o 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 airy 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 Specifications 3.0.3 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 1, 10 CFR Part 50.

Specification A implements the guides set forth in Section II.A of Appendix 1. 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 radidactive material in liquid effluents will be kept *as low as is reasonably achievable."

Amendment No.24, 90

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 arem to the total body or 0.2 arem to any organ in a 31 day period.

B.

Action:

1.

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:

a.

Explanation of why liquid radwaste was being discharged without treatment, identification of ahy inoperable equipment or.subsystems and the reason for 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 3.0.3 and 3.0.4 are not app 1icabe.

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 th.is 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 riquirements 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.T9'90

39r 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 achievabl.e.

Specification A. The air dose due to noble gases released in gaseous effluents, 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:

< S mrad for gamma radiation and < 10 mrad for beta radiation.

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

radiatiot 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 Specifications 3.0.3 and 3.0.4 are not applicable.

Basis:

This specification is provided to implement the requirements of Sections 11.8 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 that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable.'

Amendment No. 4 90

39s 3.16.3 Dose, Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form Applicability:

At all times.

Objective:

Maintain the dose due to radiolodines, 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, 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 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 Specifications 3.0.3 and 3.0.4 are not applicable.

Basis:

This specification is provided to implement the requirements of Sections 1I.C and IV.Ao6f 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. 14.90

-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 Fi.gure 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 Specifications 3.0.3 and 3.0.4 are not applicable.

Basis:

The OPERABILITY of the gaseous radwaste treatment system and the VENTILATION EXHAUST TREATMENT SYSTEM ensuresthat 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 Amendment No. 7. 90

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.8 and II.C of Appendix 1, 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:

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

2.

The provisions of Specifications 3.0.3 and 3.0.4 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 <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.

Amendment No. 4,90

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 wa"ste 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 />.

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 Specifications 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 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.19 90

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 radloactive.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 Specifications 3.0.3 and 3.0.4 are not applicable.

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.

Amendment No. ;T 90

3 9y 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 1 rovi sions of Specifications 3.0.3 and 3.0.4 are not aPpplicable.

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. T4 90

39ee

3.

The Provisions of Specifications 3.0.3 and 3.0.4 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 consumotion by a child. To determine this minimum garden size, the *following assumotions 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 Comoarison 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 of Specifications 3.0.3, 3.0.4, and 6.9.2.b(2) are not applicable.

Basis:

The requirement for participatio in an 'Interlaboratory Comoarison 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.

o4, 90

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 Specifications 3.0.3 and 3.0.4 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.

Amendment No. 4 90

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)

Q(1)

Line (R-1218)

b. Steam Generator Blowdown D

H R(3)

Q(1)

Effluent Line (R-1216)

c. Turbine Building Sumps

-D 14 R(3)

Q(l)

Effluent Line Reheater Pit Sump (R-2100*)

d..

Yard Sump (R-2101*)

D M

R(3)

Q(l)

e. Component Cooling Water D

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)

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

Amendment No.

4,90

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**) D M

R(2)

Q

b. Noble Gas Activity Monitor 0

M R(2)

Q(l)

(R-1219, 1212, 1254*)

C.

Iodine Sampler Cartridge W

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

d. Particulate Sampler Filter W

K/A N/A.

N/A (R-1211, 1220, 1254*)

e. Stack Fan Flow Indication 0

N/A Q

Q (R-1254*)

f. Sampler Flow Rate Measuring D

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.

Alarm only, does not perform any isolation function.

Amendment No.,

, 90

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 Type Frequency Frequency Analysis (uCI/ml)a P

P A. Batch Waste Each Batch Each Batch Principal Gamma S 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 Qsj Sr-89, Sr-90 5 x 10-8 Composited Fe-55 1 x 10-6 3 x W B. Continuous e Grab Sample Compositef Principal amma S x 10-7 Releases Emittersc (1) Steam Generator Slowdown 1-131 1 x 10-6 (2) Reheater Pit M

Sump Grab Sample M

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

31xW M

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. }, 90

57 TABLE 4.6.1.1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

.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 1 x 10-6 C. Plant Stack MC MI Principal Gamma I x 10-4 Grab Emittersb Sample H-3d,e 1 x 6.

Continuousf W9 1-131 1 x 10-12 Charcoal Sample Continuousf Wg Principal Gamma 1 x 10-11 Particulate Emittersb I

Sample (1-131, Others)

Continuousf M

Gross Alpha 1 x 10-11 Composite.

Particulate Sample I

Continuousf 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 Amendment No. X, 90

75b 6.5.2 NUCLEAR AUDIT AND REVIEW COMMITTEE (NARC)

FUNCTION 6.5.2.1 The NARC provides independent review and audit of designated activities in the area of nuclear safety and environmental impact.

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 Manager, Quality Assurance 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.

MEETING FREQUENCY 6.5.2.5 The NARC shall meet at least once per six months.

Amendment No.))>46 4 90

-86 (4)

Abnormal decradation of systems other than those specified i.n item 6.9.2.a.(3) above designed to contain radioactive material resultino 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 Unioue Reoortina 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, 3.1H.4 and 3.17).

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.

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 tests reveal the presence of 0.005.Ci or more of removable contamination.

Amsncer.: No. X<, Y,

/

ft8s.90

.g

- 92 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.

Amendment No.90

-93 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 100F and maintaining this temperature for approximately two hours once every five to six weeks and occasionally once every four weeks, 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 discharce 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.

Amendment No. 90

-94 A 12-foot ID reinforced concrete conduit is connected horizontally to the shoreward side of the discharge 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 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.

Amendment No.

90

W

- 95 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.

Amendment No. 90