ML20042D364

NRC-2020-000134 - Resp 1 - Final, Agency Records Subject to Request Enclosed, Part 1 of 2

ML20042D364
Person / Time
Site:	San Onofre
Issue date:	02/06/2020
From:	NRC/OCIO
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ML20042D360	List: ML20042D363 ML20042D364 ML20042D365
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NRC-2020-000134
Download: ML20042D364 (57)

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LICXSE AUIHO0ITY FILL COY 2 O..E UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE License No NPF-10

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

A. The application for license filed by the Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside, California and The City of Anaheim, California (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I. and all required notifications to other agencies or bodies have been duly made:

B. Construction of the San Onofre Nuclear Generating Station. Unit 2 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-97 and the application as amended. the provisions of the Act, and the regulations of the Commission:

--/ C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission:

D. There is reasonable assurance: (i)that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii)that such activities will be conducted in compliance with the regulations of the Commission set forth in 10 CFR Chapter I:

E. The Southern California Edison Company* is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth In 10 CFR Chapter I:

F. The licensees are financially qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter 1:

• The Southern California Edison Company is authorized to act as agent for the other co-owners and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

Amendment No. 185

<<X9 g 4 &6g~a~

G. The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; H. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; I. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-10, subject to the condition for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and J. The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accordance with the Commission's* regulations in 10 CFR Parts 30, 40 and 70.

2. Based on the foregoing findings and the Partial Initial Decision issued by the Atomic Safety and Licensing Board on January 11, 1982, regarding this facility, Facility Operating License No. NPF-10 is hereby issued to the Southern California Edison Company, the San Diego Gas and Electric Company, the City of Riverside, California, and the City of Anaheim, California 1 to read as follows:

A. This license applies to the San Onofre Nuclear Generating Station, Unit 2, a pressurized water nuclear reactor and associated equipment (the facility), owned by the licensees. The facility is located in San Diego County, California, and is described in the Final Safety Analysis Report as supplemented and amended, and the Environmental Report, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside, California, and the City of Anaheim, California 1 to possess the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; (2) Southern California Edison Company (SCE), pursuant to Section 103 of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess and use the facility at the designated location in San Diego County, California in accordance with the procedures and limitations set forth in this license; 1The City of Anaheim has transferred its ownership interests in the facility, and entitlement to facility output, to Southern California Edison Company, except that it retains its ownership interests in its spent nuclear fuel and the facility's independent spent fuel storage installation located on the facility's site. In addition, the City of Anaheim retains financial responsibility for its spent fuel and for a portion of the facility's decommissioning costs. The City of Anaheim remains a licensee for pwposes of its retained interests and liabilities.

Amendment No. 230

(3) SCE, pursuant to the Act and 10 CFR Part 70, to possess at any time special nuclear material that was used as reactor fuel, in accordance with the limitations for storage, as described in the Final Safety Analysis Report, as supplemented and amended; (4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; and possess any byproduct, source and special material as sealed neutron sources that was used for reactor startup; (5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 2 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to al; applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Deleted (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 235, are hereby incorporated in the license.

Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 235

(3) Antitrust Conditions SCE shall comply with the antitrust conditions delineated in Appendix C to this license.

(4) Containment Tendon Surveillance (Section *3.8.1. SER. SSER Deleted by Amendment No. 37 (5) Environmental Qualification (Section 3.11. SER. SSER #3, SSER Deleted by Amendment No. 60 (6) High Burnup Fission Gas Release (Section 4.2.2.2. SER)

Deleted by Amendment No. 185 (7) Low Temperature Overpressurization Protection (Section 5.2.2.2. SER)

Deleted by Amendment No. 185 (8) Control Room Pressurization Capability (Section 6.4. SER.

SSER #5)

Deleted by Amendment No. 185 (9) Seismic Trin System (Section 7.2.5. SSER #4)

Deleted by Amendment No. 185 (10) Volume Control Tank Control Logic (Section 7.3.5. SSER #4)

Deleted by Amendment No. 185 (11) Compliance with Regulatorv Guide 1.97 (Section 7.5.1, SER.

SSER #5)

Deleted by Amendment No. 185 (12) Control System Failures (Section 7.7. SSER #4)

Deleted by Amendment No. 185 (13) Diesel Generator Modifications (Section 8.3.1. SER)

Deleted by Amendment No. 185

• The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. 185 Nwj (i~- 8~o gSlDS

(14) Deleted (15) Turbine Disc Inspection (Section 10.2.2. SER)

Deleted by Amendment No. 185 (16) Radioactive Waste System (Section 11.1. SER. SSER #5)

Deleted by Amendment No. 185 (17) Purge System Monitors (Section 11.3. SER. SSER #5)

Deleted by Amendment No. 185 (18) Initial Test Program (Section 14. SER)

Deleted by Amendment No. 185 (19) NUREG-0737 Conditions (Section 22)

a. Shift Technical Advisor (l.A.1.1. SSER #1)

• Deleted by Amendment No. 185

b. Shift Manning (1.A.1.3. SSER #1. SSER #5)

Deleted by Amendment No. 147

c. Independent Safety Engineering Group (1.B.1.2. SSER #1)

Deleted by Amendment No. 185

d. Procedures for Transients and Accidents (l.C.1. SSER #1.

SSER #2. SSER #5)

Deleted by Amendment No. 185 Amendment No. 230

e. Procedures for Verifying Correct Performance of Operating Activities (U.C.6. SSER #1)

Deleted by Amendment No. 185 I

f. Control Room Design Review (I.D.1. SSER #1)

Deleted by Amendment No. 185 I

9. Special Low Power Testing and Training (I.G.1. SSER #1)

Deleted by Amendment No. 185

h. Reactor Coolant System Vents (II.B.1). SSER #1 , SSER t4l Deleted by Amendment No. 185

1. Post-Accident Sampling System (NUREG-0737 Item II.B.3)

Deleted by Amendment No. 178 I i- Safety Valve Test Requirements (II.D.1, SSER #1)

Deleted by Amendment No. 185

k. Direct Indication of Safety Valve Position (JI.D.3, SSER

~11 Deleted by Amendment No. 185

1. AFW Pump 48-hour Endurance Test (II.E.1.1, SSER #1)

Deleted by Amendment No. 185

m. Emergency Power Supplv for Pressurizer Heaters (Il.E.3.1. SSER #1. SSER #5)

Deleted by Amendment No. 185

n. Additional Monitoring Instrumentation (II.F.1, SSER #1.

SSER #4)

Deleted by Amendment No. 185

0. ICC Instrumentation (II.F.2. SSER #1, SSER #2. SSER #4)

Deleted by Amendment No. 185 p- Voiding in the Reactor Coolant System (II.K.2.17, SSER

-#I. SSER #5)

Deleted by Amendment No. 185 I q- Revised Model for Small-Break LOCAs (II.K.3.30. SSER #1, SSER #4.SSER #5 Deleted by Amendment No. 185 I Amendment No. 185 Cat-~w A, o6 Q-g

r. Plant-Specific Calculations for Compliance with 10 CFR Section 50.46 (l1.K.3.31, SSER #1)

Deleted by Amendment No. 185 S. Improving Licensee Emergency Preparedness (III.A.2, SSER#1, SSER #5)

Deleted by Amendment No. 185 (20) Surveillance Program (Section 1.12, SSER #5)

Deleted by Amendment No. 185 (21) Laboratory Instrumentation (Section 1.12, SSER #5)

Deleted by Amendment No. 185 (22) Design Verification Program (Section 3.7.4. SSER #5)

Deleted by Amendment No. 185 (23) Emergency Preparedness Conditions Deleted by Amendment No. 185 (24) RCS Depressurization System (PORV's)

Deleted by Amendment No. 185 (25) Qualification of Auxiliary Feedwater (AFW) Pump Motor Bearings Deleted by Amendment No. 185 (26) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment Amendment No. 185 Revised by letter dated July 26, 2007

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (27) Deleted (28) Prior to February 16, 2021, if all spent fuel has not been removed from the Unit 2 spent fuel pool, an aging-management program shall be submitted for NRC approval. The scope of the program shall include those long-lived, passive structures and components that are needed to provide reasonable assurance of the safe condition of the spent fuel in the spent fuel pool. Once approved, the program shall be described in the Updated Final Safety Analysis Report and shall remain in effect for Unit 2 until such time that all spent fuel has been removed from the Unit 2 spent fuel pool.

D. Exemptions to certain requirements of Appendices G, Hand J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission.

Amendment No. 230

E. SCE shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled: "San Onofre Nuclear Generating Station Security, Training and Qualification, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 15, 2006.1 Pursuant to NRC's Order EA-13-092, dated June 5, 2013, NRC reviewed and approved the license amendment 232 that permitted the security personnel of the licensee to possess and use certain specific firearms, ammunition, and other devices, such as large-capacity ammunition feeding devices, notwithstanding local, State, and certain Federal firearms laws that may prohibit such possession and use.

F. This license is subject to the following additional condition for the protection of the environment:

Before engaging in activities that may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evaluated in the Final Environmental Statement, SCE shall provide a written notification of such activities to the NRC Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities.

G. DELETED H. SCE shall notify the Commission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.

I. SCE shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

J. Deleted i

• On September 29, 1983, the Safeguards Contingency Plan was made a separate, companion document to the Physical Security Plan pursuant to the authority of 10 CFR 50.54.

Amendment No. 235

3. On June 12, 2013, Southern California Edison (SCE) certified that operations at San Onofre Nuclear Generating Station Unit 2 would permanently cease in accordance with 10 CFR 50.82(a)(1 )(i). On July 22, 2013, SCE certified that the fuel had been permanently removed from the reactor vessel in accordance with 10 CFR 50.82(a)(1)(ii).

As a result, the 1O CF:R 50 license no longer authorizes operation of the reactor, or the emplacement or retention of fuel in the reactor vessel.

This license is effective as of the date of issuance and authorizes ownership and possession of San Onofre Nuclear Generating Station Unit 2 until the Commission notifies the licensee in writing that the license is terminated. The licensee shall:

A. Take actions necessary to decommission the plant and continue to maintain the facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition; and B. Conduct activities in accordance with all other restrictions applicable to the facility in accordance with the NRC regulations and the applicable provisions of the 10 CFR 50 facility license as defined in Section 2 of this license.

FOR THE NUCLEAR REGULA TORY COMMISSION Original Signed by Harold R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Appendix A (Technical Specifications)

2. Appendix B (Environmen~al Protection Plan)

3. Appendix C (Antitrust Conditions)

Date of Issuance: FEB 16 1982 Amendment No. 230

APPENDIX A TO THE FACILITY OPERATING LICENSE NPF-10 AND FACILITY OPERATING LICENSE NPF-15 TECHNICAL SPECIFICATIONS FOR SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 AND UNIT 3

TABLE OF CONTENTS 1.0 USE AND APPLICATION ................................................................................... 1.1-1 1.1 Definitions ................................................................................................... 1.1-1 1.2 Logical Connectors ..................................................................................... 1.2-1 1.3 Completion Times ...................................................................................... 1.3-1 1.4 Frequency .................................................................................................. 1.4-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .................................. 3.0-2 3.1 PLANT SYSTEMS .............................................................................................. 3.1.1-1 3.1.1 Fuel Storage Pool Water Level .................................................................. 3.1.1-1 3.1.2 Fuel Storage Pool Boron Concentration ..................................................... 3.1.2-1 3.1.3 Spent Fuel Assembly Storage .................................................................... 3.1.3-1 4.0 DESIGN FEATURES .......................................................................................... 4.0-1 4.1 Site ............................................................................................................. 4.0-1 4.2 Deleted ....................................................................................................... 4.0-1 4.3 Fuel Storage ............................................................................................... 4.0-4 5.0 ADMINISTRATIVE CONTROLS ......................................................................... 5.0-1 5.1 Responsibility ............................................................................................. 5.0-1 5.2 Organization ............................................................................................... 5.0-2 5.3 Facility Staff Qualifications ......................................................................... 5.0-5 5.4 Technical Specifications (TS) Bases Control ............................................. 5.0-6 5.5 Procedures, Programs, and Manuals ......................................................... 5.0-7 5.6 Deleted ....................................................................................................... 5.0-11 5.7 Reporting Requirements ............................................................................ 5.0-12 5.8 High Radiation Area .................................................................................. 5.0-14 Unit 2-Amendment 230 San Onofre Unit 3-Amendment 223

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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N 0 TE-----------------------------------------------------------

T he defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CERTIFIED FUEL HANDLER A CERTIFIED FUEL HANDLER is an individual who complies with provisions of the CERTIFIED FUEL HANDLER training program required by TS 5.3.2.

OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

Unit 2-Amendment 230 San Onofre 1 .1-1 Unit 3-Amendment 223

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLE The following example illustrates the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify ...

A.2 Restore ...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Unit 2 - Amendment 230 San Onofre 1.2-1 Unit 3 - Amendment 223

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Condition for Operation (LCOs) specify minimum requirements for ensuring safe storage of fuel assemblies. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the facility is in a specified condition stated in the Applicability of the LCO.

Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the facility is not within the LCO Applicability.

EXAMPLE The following example illustrates the use of Completion Times.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Verify ... 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Action and associated Completion Time not met. B.2 Restore ... 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition Bis entered.

The Required Actions of Condition B are to perform the verification within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> AND perform the restoration within 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br />. A total of 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> is allowed for performing the verification and a total of 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (not 42 hours1.75 days <br />0.25 weeks <br />0.0575 months <br />) is allowed for performing the restoration from the time that Condition B was entered. If verification is performed within 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br />, the Unit 2 - Amendment 230 San Onofre 1.3-1 Unit 3 -Amendment 223

Completion Times 1.3 1.3 Completion Times EXAMPLE (continued) time allowed for performing the restoration is the next 33 hours1.375 days <br />0.196 weeks <br />0.0452 months <br /> because the total time allowed for performing the restoration is 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br />.

• IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner.

TIME Unit 2 - Amendment 230 San Onofre 1.3-2 Unit 3 -Amendment 223

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) occurs whenever any fuel assembly is stored in the fuel storage pool.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify ... 7 days Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (7 days) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 7 days, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the facility is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a specified condition in the Applicability of the LCO, then SR 3.0.3 becomes applicable.

Unit 2 - Amendment 230 San Onofre 1.4-1 Unit 3-Amendment 223

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify ... Prior to moving a fuel assembly ...

Example 1.4-2 illustrates a one time performance Frequency.

This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.

Unit 2 - Amendment 230 San Onofre 1.4-2 Unit 3 - Amendment 223

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s} is not required, unless otherwise stated.

Unit 2-Amendment 230 San Onofre 3.0-1 Unit 3-Amendment 223

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. The Completion Times of the Required Actions begin immediately upon expiration of the delay period.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. The Completion Times of the Required Actions begin immediately upon failure to meet the Surveillance.

SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with ACTIONS.

Unit 2-Amendment 230 San Onofre 3.0-2 Unit 3-Amendment 223

Fuel Storage Pool Water Level 3.1 .1 3.1 PLANT SYSTEMS 3.1.1 Fuel Storage Pool Water Level LCO 3.1.1 The fuel storage pool water level shall be ~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool water A.1 Suspend movement of fuel Immediately level not within limit. assemblies in fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify the fuel storage pool water level is ~ 23 ft 7 days above the top of irradiated fuel assemblies seated in the storage racks.

Unit 2-Amendment 230 San Onofre 3.1.1-1 Unit 3-Amendment 223

Fuel Storage Pool Boron Concentration 3.1.2 3.1 PLANT SYSTEMS 3.1.2 Fuel Storage Pool Boron Concentration LCO 3.1.2 The fuel storage pool boron concentration shall be :::: 2000 ppm.

APPLICABILITY: Whenever any fuel assembly is stored in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool boron A.1 Suspend movement of fuel Immediately concentration not within assemblies in the fuel limit. storage pool.

A.2 Initiate action to restore fuel Immediately storage pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify the fuel storage pool boron concentration is 7 days within limit.

Unit 2-Amendment 230 San Onofre 3.1.2-1 Unit 3-Amendment 223

Spent Fuel Assembly Storage 3.1.3 3.1 PLANT SYSTEMS 3.1.3 Spent Fuel Assembly Storage LCO 3.1.3 The combination of initial enrichment and burnup of each SONGS 2 and 3 spent fuel assembly stored in Region I shall be within the acceptable burnup domain of Figure 3.1.3-1 or Figure 3.1.3-2 or the fuel assembly shall be stored in accordance with Technical Specification 4.3.1.1.

The combination of initial enrichment and burnup of each SONGS 2 and 3 spent fuel assembly stored in Region II shall be within the acceptable burnup domain of Figure 3.1.3-3 or Figure 3.1.3-4, or the fuel assembly shall be stored in accordance with Technical Specification 4.3.1.1.

Each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be stored in accordance with Technical Specification 4.3.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Initiate action to bring the Immediately LCO not met. noncomplying fuel assembly into compliance.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify by administrative means the initial Prior to moving a enrichment, burn up, and cooling time of the fuel fuel assembly to assembly are in accordance with LCO 3.1.3, or any spent fuel Design Features 4.3.1.1, or Licensee Controlled pool storage Specification (LCS) 4.0.100. Rev 2, dated 09127107. location.

Unit 2 - Amendment 230 San Onofre 3.1.3-1 Unit 3 - Amendment 223

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-1 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION I RACKS 25 Acceptable Region Unacceptable Region 0 ~--~---~~-~~~~~-~~-~~-

2. 0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)

-B- O Years ~ 5 Years ---9-- 10 Years~ 15 Years--H- 20 Years Unit 2-Amendment 230 San Onofre 3.1.3-2 Unit 3-Amendment 223

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-2 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONS IN REGION I RACKS 15 i='

0 s

Q, 1 o Acceptable Region 0.

i E

i ID

0 E

Q)

~ 5

<(

Qi

i Unacceptable Region u..

0 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)

-a- o Years ~ 5 Years ~ 1O Years-fr- 15 Years~ 20 Years Unit 2-Amendment 230 San Onofre 3.1.3-3 Unit 3-Amendment 223

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-3 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS 60

• t>u Acceptable Region r5

~~

~.40

=;Ci..

~

E tJ

~ 20 Unacceptable Region ....

0 2 3 4 5

!ni!lal U-235 Emichrm:mt {wfo)

-=- 0 Years - 5 Yoars - 10 Years .....:...;_ 15 Years _,,,,;,;;_ 20 Yoars Unit 2-Amendment 230 San Onofre 3.1 .3-4 Unit 3-Amendment 223

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-4 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONS IN REGION II RACKS 4!J Acceptable Region Vnacceptabl~ Region 0

4 5 3 35 Unit 2-Amendment 230 San Onofre 3.1.3-5 Unit 3-Amendment 223

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Exclusion Area Boundary The exclusion area boundary shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be as shown in Figure 4.1-2.

4.2 Deleted.

Unit 2-Amendment 230 San Onofre 4.0-1 Unit 3-Amendment 223

Design Features 4.0 4.0 DESIGN FEATURES (continued)

I

\\

I I 200 0 s

0 C E A N

/

Figure 4.1-1(page1of1)

Exclusion Area Boundary Unit 2-Arnendment 230 San Onofre 4.0-2 Unit 3-Amendment 223

Design Features 4.0 4.0 DESIGN FEATURES (continued)

Figure 4.1-2 (page 1 of 1)

Low Population Zone Unit 2-Amendment 230 San Onofre 4.0-3 Unit 3-Amendment 223

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent;

b. Kett < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

c. Kett::; 0.95 if fully flooded with water borated to 1700 ppm, which includes an allowance for uncertainties as described in Section 9 .1 of the UFSAR;

d. Three or five Borated stainless steel guide tube inserts (GT-Insert) may be used. When three borated stainless steel guide tube inserts are used, they will be installed in an assembly's center guide tube, the guide tube associated with the serial number, and the diagonally opposite guide tube. Fuel containing GT-Inserts may be placed in either Region I or Region II. However, credit for GT-Inserts is only taken for Region II storage.

A five-finger CEA may be installed in an assembly. Fuel containing a five-finger CEA may be placed in either Region I or Region II. Credit for inserted 5-finger CEAs is taken for both Region I and Region II.

e. A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II;

f. A nominal 10.40 inch center to center distance between fuel assemblies placed in Region I;

g. Prior to using the storage criteria of LCO 3.1.3 and LCS 4.0.100, the following uncertainties will be applied:

(1) The calculated discharge burnup of San Onofre Units 2 and 3 assemblies will be reduced by 6.6%.

(2) The calculated discharge burnup of San Onofre Unit 1 fuel assemblies will be reduced by 10.0%.

Unit 2-Amendment 230 San Onofre 4.0-4 Unit 3-Amendment 223

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

h. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-1 are allowed unrestricted storage in Region I;

i. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-2 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region I;

j. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-3 are allowed unrestricted storage in Region II;

k. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-4 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region II; I. Units 2 and 3 fuel assemblies with a burnup in the "unacceptable range" of Figure 3.1.3-1, Figure 3.1.3-2, Figure 3.1.3-3, and Figure 3.1.3-4 will be stored in compliance with Licensee Controlled Specification 4.0.100 Rev. 2, dated 9127107; and

m. Each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be stored in accordance with Licensee Controlled Specification 4.0.100 Rev. 2, dated 9127107.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Technical Specification 3.1.1 value (23 feet above the top of irradiated fuel assemblies seated in the storage racks).

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.

Unit 2-Amendment 230 San Onofre 4.0-5 Unit 3-Amendment 223

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The corporate officer with direct responsibility for the plant shall be responsible for overall management of the San Onofre Nuclear Generating Station, and all site support functions. He shall delegate in writing the succession to this responsibility during his absence.

5.1.2 The Shift Manager shall be responsible for the ultimate command decision authority for all unit activities which affect the safety of the plant, site personnel, and/or the general public.

Unit 2-Amendment 230 San Onofre 5.0-1 Unit 3-Amendment 223

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The on site and offsite organizations shall include the positions for activities affecting the safety of the nuclear fuel.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These relationships, including the plant-specific titles of those personnel fulfilling the responsibilities for the positions delineated in these Technical Specifications, are documented in the UFSAR.

b. The corporate officer with direct responsibility for the plant shall be responsible for overall safe handling and storage of nuclear fuel and shall have control over those onsite activities necessary for safe handling and storage of the nuclear fuel.

c. A specified corporate officer (or officers) shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure safe management of nuclear fuel.

d. The individuals who train CERTIFIED FUEL HANDLERS, and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.

5.2.2 FACILITY STAFF The facility staff organization shall include the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 5.2.2-1.

b. At least one person qualified as Emergency Coordinator/Emergency Director shall be in the Control Room when nuclear fuel is stored in the spent fuel pools.

Unit 2 - Amendment 230 San Onofre 5.0-2 Unit 3 - Amendment 233

Organization 5.2 5.2 Organization 5.2.2 FACILITY STAFF (continued)

c. Shift crew composition may be less than the minimum requirement of Table 5.2.2-1 for a period of time not to exceed 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements. During such absences, no fuel movement or movement of heavy loads over storage racks containing fuel is permitted.

d. Oversight of fuel handling operations shall be provided by a CERTIFIED FUEL HANDLER.

e. The Shift Manager shall be a CERTIFIED FUEL HANDLER.

f. An individual qualified in radiation protection procedures shall be on site during fuel handling operations or movement of loads over the storage racks containing fuel.

Unit 2 - Amendment 230 San Onofre 5.0-3 Unit 3 - Amendment 233

Organization 5.2 5.2 Organization (continued)

Table 5.2.2-1 Minimum Shift Crew Composition POSITION MINIMUM STAFFING CERTIFIED FUEL HANDLER 1*

Certified Operator 1 Note: The Certified Operator position may be filled by a CERTIFIED FUEL HANDLER.

• May be shared between Units 2 and 3.

Unit 2 - Amendment 230 San Onofre 5.0-4 Unit 3 - Amendment 233

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except: a) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

5.3.2 An NRC approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

Unit 2-Amendment 230 San Onofre 5.0-5 Unit 3-Amendment 223

TS Bases Control 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Technical Specifications (TS) Bases Control 5.4.1 Changes to the Bases of the TS shall be made under appropriate administrative controls.

5.4.2 Changes to the Bases may be made without prior NRC approval provided the changes do not require either of the following:

a. A change in the TS incorporated in the license; or

b. A change to the updated UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

5.4.3 The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

5.4.4 Proposed changes that meet the criteria of (a) or (b) above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC every 24 months.

Unit 2-Amendment 230 San Onofre 5.0-6 Unit 3-Amendment 223

Procedures, Programs, and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures, Programs, and Manuals 5.5.1 Procedures 5.5.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory guide 1.33, Revision 2, Appendix A, February 1978;

b. Deleted.

c. Quality assurance for effluent and environmental monitoring using the guidance in Regulatory Guide 4.15, Revision 1, 1979;

d. Fire Protection Program implementation; and

e. Programs, as specified in Specification 5.5.2.

5.5.2 Programs and Manuals The following programs and manuals shall be established, implemented, and maintained.

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program;

b. The ODCM shall also contain the Radioactive Effluent Controls required by Specification 5.5.2.3 and Radiological Environmental Monitoring programs required by the LCS, and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 5.7.1.2 and Specification 5. 7 .1.3.

5.5.2.1.1 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

Unit 2 - Amendment 230 San Onofre 5.0-7 Unit 3 - Amendment 223

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.1.1 Licensee-initiated changes to the ODCM (continued):

1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable.

b. Shall become effective upon review and approval by the corporate officer with direct responsibility for the plant or designee.

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2.2 Deleted 5.5.2.3 Radioactive Effluent Controls Program This program conforming to 10 CFR 50.36a provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by operating procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 CFR 20, Appendix B, Table II, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM; Unit 2 - Amendment 230 San Onofre 5.0-8 Unit 3 -Amendment 223

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.3 Radioactive Effluent Controls Program (continued)

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.2.4 Deleted 5.5.2.5 Deleted 5.5.2.6 Deleted Unit 2 -Amendment 230 San Onofre 5.0-9 Unit 3 - Amendment 223

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.7 Storage Tank Radioactivity Monitoring Program This program provides controls for the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15. 7 .3, "Postulated Radioactive Release due to Tank Failures".

The program shall include a surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Waste Management System is less than the amount that would result in concentrations less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Storage Tank Radioactivity Monitoring Program surveillance frequencies.

Unit 2 - Amendment 230 San Onofre 5.0-10 Unit 3 - Amendment 223

5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Deleted Unit 2-Amendment 230 San Onofre 5.0-11 Unit 3-Amendment 223

Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.1 Routine Reports In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4. The reports shall be addressed to the U.S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D.C., with a copy to the Regional Administrator of the Regional Office of the NRC, unless otherwise noted.

5.7.1.1 Deleted 5.7.1.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.8.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. The report shall identify the thermoluminescent dosimeter (TLD) results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

Unit 2-Amendment 230 San Onofre 5.0-12 Unit 3-Amendment 223

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.3 Radiological Effluent Release Report The Radioactive Effluent Release Report covering the operation of the facility during the previous calendar year shall be submitted before May 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the facility. The report shall also include a summary of the quantities of solid radioactive waste shipped from the facility directly to the disposal site and quantities of solid radioactive waste shipped from the facility's intermediary processor to the disposal site. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program (PCP) and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

Unit 2-Amendrnent 230 San Onofre 5.0-13 Unit 3-Amendment 223

High Radiation Area 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 High Radiation Area 5.8.1 Each high radiation area as defined 10 CFR 20 shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP).

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area,

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rates in the area have been determined and personnel have been made knowledgeable of them,

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device. This individual is responsible for providing positive radiation protection control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation protection procedures or the applicable REP.

5.8.2 In addition, areas that are accessible to personnel and that have radiation levels greater than 1.0 rem (but less than 500 rads at 1 meter) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source, or from any surface penetrated by the radiation, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift manager on duty or radiation protection supervisor. Doors shall remain locked except during periods of access by personnel under an approved REP that specifies the dose rates in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of a stay time specification on the REP, direct or remote continuous surveillance (such as closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could result in radiation doses greater than 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and that are within large areas where no enclosure exists to enable locking and where no enclosure can be reasonably constructed around the individual area shall be barricaded and conspicuously posted. A flashing light shall be activated as a warning device whenever the dose rate in such an area exceeds or is expected to exceed 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface penetrated by the radiation.

Unit 2-Amendment 230 San Onofre 5.0-14 Unit 3-Amendment 223

LICENSE AUTHORI FILE COPY, DO NOT REMOVE 5°%

APPENDIX B e4tv° a-/6-ia.

TO FACILITY LICENSE NO. NPF-1O FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA AND THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 ENVIRONMENTAL PROTECTION PLAN FEBRUARY 1982

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TABLES OF CONTENTS Section PAGE 1.0 Objectives of the Environmental Protection Plan ................ 1-1 2.0 Environmental Protection Issues ................................ 2-1 2.1 Aquatic Issues ............................................ 2-1 2.2 Terrestrial Issues ........................................ 2-1 2.3 Cultural Resources Issues ................................. 2-1 3.0 Consistency Requirements ....................................... 3-1 3.1 Plant Design and Operation ................................ 3-1 3.2 Reporting Related to the NPDES Permits and State Certification ........................................... 3-2 3.3 Changes Required for Compliance with Other Environmental Regulations ............................................. 3-2 4.0 Environmental Conditions . ...................................... 4-1 4.1 Unusual or Important Environmental Events . ........... 4-1 4.2 Environmental Protection Programs . ............... 4-1 4.2.1 Cultural Resources Data Recovery Program ........... 4-1

1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of environ-mental values during construction and operation of the nuclear facility. The principal objectives of the EPP are as follows:

(1) Verify that the plant is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other Federal, State and local requirements for environmental protection.

(3) Keep NRC informed of the environmental effects of facility construction and operation and of actions taken to control those effects.

Environmental concerns identified in the FES which relate to water quality matters are regulated by way of the licensee's NPDES permit.

1-1

2.0 Environmental Protection Issues In the FES-OL dated April 1981, the staff has considered the environmental impacts associated with the operation of the San Onofre Nuclear Generating Station. Certain environmental issues were identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of the environment.

2.1 Aquatic Issues (1) The need for aquatic monitoring programs to ensure protection of the San Onofre kelp bed (FES-OL, Sections 5.4.2.1 and 6.3.1).

(2) The need for continuation of the ichthyoplankton study until such time as it is possible to state credibly that no significant impacts result from the facility (FES-OL, Section 6.3.1).

(3) The need for a program for optimizing the effectiveness of the fish return system (FES-OL, Section 6.3.1).

Aquatic issues are to be addressed by the effluent limitations, monitoring requirements and demonstration studies contained in the effective NPDES permit issued by the California Regional Water Quality Control Board-San Diego Region.

The NRC will rely on that agency for regulation of matters involving water quality and aquatic biota.

2.2 Terrestrial Issues None.

2.3 Cultural Resources Issues (1) The need to protect the archeological sites within the 230 kV transmission line right-of-way which were identified to be eligible for the National Register of Historic Places.

2-1'

3.0 Consistency Requirements

• 3.1 Plant Design and Operation The licensee may make changes in station design or operation or perform tests or experiments'affecting the environment provided such changes, tests or experiments do not involve an unreviewed environmental question. Changes in plant design or operation or performance of tests or experiments which do not affect the environment are not subject to this requirement. Activities governed by Section 3.3 are not subject to the requirements of this section.

Before engaging in unauthorized construction or operational activities which may affect the environment, the licensee shall prepare and record an environmental evaluation of such activity.* When the evaluation indicates that such activity involves an unreviewed question, the licensee shall provide a written evaluation of such activities and obtain prior approval from the NRC.

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement (FES) as modified by the staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level (in accordance with 10 CFR Part 51.5(b)(2)) or (3) a matter not previously reviewed and evaluated in the documents specified in (1) of this subsection, which may have a significant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this subsection. These records shall include a written evaluation which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question.

"Wtivities are excluded from this requirement if all measurable nonradiological effects are confined to the on-site areas previously disturbed during site prep-aration and plant construction.

3-1

. Z-X o

.r. I UFLIIIy ArIaLCU Lo Tne nrutz re-nits anu znaTe 1erLLTCaTIlOns 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 withinW30 days following the date the stay is granted.

3.3 Changes Required for Compliance with Other Environmental Regulations '

Changes in plant design or operation.and performance of tests or experiments which are required to achieve compliance with other Federal, State, or local environmental regulations are not subject to the requirements of Section 3.1.

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4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an. unusual or important event that indicates or could result

• n significant environmental impact' causally related to station operation shall be recorded 'and promptly reported'to the NRC within 24 hours1 days <br />0.143 weeks <br />0.0329 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 'ofthe 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 al.so 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 as soon as practical but no later than 30 days after it is submitted to the other agency. lI 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; ncrease.in nuisance-organisms or conditions; and unanticipated or emergency discharge 'of waste water or chemical substances.

4.2 Environmental Protection Program 4.2.1 Cultural Resources Data Recovery Program Fourteen archeological sites have been identified within the San Onofre 230 kV transmission line rights-of-way'which'.have been determined to be eligible for the National Register of Historic Places. It has been agreed by the NRC, the 4-1 . 168 :'

State Historic Preservation Officer (SHPO) and the licensee that the 14 sites would be adversely affected by the expected operation and maintenance activities of the licensee. It was further agreed that the appropriate action to be taken-for negating the adverse effects would be a data recovery program; such action would permit documentation of "no adverse effect" determinations.

The licensee is required to provide the NRC with a data recovery program which has been developed in consultation with the SHPO and concurred in by the SHPO. The 14 sites involved in the data recovery program are designated as ORA-495, ORA-4.96, ORA-499, ORA-825, ORA-830, ORA-831, SDi-6140, ORA-824, ORA-498, SDi-6130, SDi-6149, ORA-447, ORA-725, and ORA-438. The applicant will follow the guidelines presented in "Treatment of Archeological. Properties, A Handbook" published by the Advisory Council on Historic Preservation (ACHP),

November 1980 and in the Code of Federal Regulations referred to therein.

After ACHP comment is received by the NRC, the data recovery program will be revised, if necessary, to incorporate any comments provided by the ACHP. The applicant will then proceed, in consultation with the SHPO, to implement the data recovery program. Upon completion of the data recovery program, a report shall be submitted to the NRC which will include a description of the results of the program and the disposition of the data recovered. Upon submittal of this report, this section of the EPP is fully satisfied with no further action required.

4-2

• .LICENSE AUTHORITY FILE CO NOT REMOVE APPENDIX C .

ANTITRUST CONDITIONS M -/6 LICENSE NO. NPF-10 The Southern California Edison Company shall comply with the following antitrust conditions:

1. As .used herein:

1.1 "Bulk Power" means the electric power, and any attendant energy, supplied or made available Mt transmission or sub-transmission voltage by one entity to another.

1.2 "Entity" means a person, a private or public corpora-tion, a municipality, a cooperative, an association, a joint stock association or business trust owning, operating or proposing in good faith to own or operate equipment or facilities for the generation, trans-mission or distribution of electricity to or for the public as a ut lity.

2. Southern California Edison (hereafter SCE) recognizes it is generally in the public interest for electric utilities to interconnect, coordinate reserves, and/or engage in bulk power supply transactions in order to provide mutual, though not necessarily equal benefits, to each of the parties in such arrangements. However, SCE should not be obligated to enter into such an arrangement if (1) to do so would violate, or incapacitate it from performing any lawfully existing contracts it has with another party or (2) there is contemporaneously available to it a mutually exclusive competing or alternative arrangement with another party which affords it greater benefits. In implementing the commitments in the succeeding paragraphs, SCE will act in accordance with these principles.

3. SCE shall, pursuant to such principles, permit participation on mutually agreeable terms in new nucleargenerating units initiated by SCE, upon timely applicationa by any entity(ies) within or contiguous to SCE's service area which at that time does not have access to an alternative comparably-priced source of bulk power supply. With respect to those units not initiated by SCE in which SCE is a joint participant with other utilities, SCE shall cooperate in facilitating the participation of any such entity(ies) which seeks such parti-cipation upon timely application.

4. SCE shall permit interconnection and coordination of reserves by means of agreements for the sale and purchase of emergency bulk power with any entity(ies) within or contiguous to SCE's service area and thereby allow such other entity(ies),

as well as SCg, full access on a proportionate basis to the benefits of reserve coordination. ("Proportionate basis" refers to the equalized percentage of reserves concept rather than the largest single-unit concept, unless the participants have otherwise agreed.) Interconnections will not be limited to low voltages when higher voltages are available from SCE's installed facilities in the area where interconnection is desired, when the proposed arrangement is found to be functionally, technically and economically feasible. Emer-gency service to be provided under such agreements will be furnished to the fullest extent available and desired where such supply does not jeopardize or impair service to the supplier's customers.

5. SCE shall sell bulk power to or purchase bulk power from any other entity(ies) within or contiguous to SCE's service area.

This refers to the mutually beneficial opportunity to coordinate in the planning of new generation, related trans-mission and associated facilities. This provision shall not be construed to require SCE to purchase or sell bulk power if such purchase or sale cannot be found to be functionally, technically and economically feasible.

-/With respect to SCE's present or future resale customers "timely application" shall be in no event later than 90 days after ptiblica-tion by the Atomic Energy Commission of the notice of the receipt of application for a construction permit. With respect to all other entity(ies) referred to above "timely application" shall be within a reasonable period from a planning standpoint after the first public announcement of SCE's intention to construct the specific unit, but in no event later than the said time specified for SCE's resale customers.

6. SCE shall, pursuant to such principles, transmit bulk power over its transmission facilities within its service area, both between or among two or more entities with which it is interconnected to the extent that such transmission can be found to be functionally, technically and economically feasible and can be effected without an adverse effect on service to its own customers. SCE is obligated under this condition to transmit bulk power on the terms stated above, and in connection with SCE's plan to construct new trans-mission facilities for its own use within its service area, to include in its planning and construction program sufficient transmission capacity as required for such transmission, provided that such entity(ies) are obligated to compensate SCE fully for the use of its system. SCE shall use its best efforts to facilitate the transmission of bulk power over then existing transmission facilities outside its service area for such entities.

7. The foregoing conditions shall be implemented in a manner consistent with the provisions of the Federal Power Act and all rates, charges, or practices in connection thereprith are to be subject to the approval of regulatory articies having jurisdiction over them.