ML20042D365

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NRC-2020-000134 - Resp 1 - Final, Agency Records Subject to Request Enclosed, Part 2 of 2
ML20042D365
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 02/06/2020
From:
NRC/OCIO
To:
Shared Package
ML20042D360 List:
References
FOIA, NRC-2020-000134
Download: ML20042D365 (19)
v • d • e


Text

LICE-SSE AUTIM2I1TY FILL CO--'

UNITED STATES DONOT RD-'OVE NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT 3 FACILITY OPERATING LICENSE License No. NPF-15

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

A. The application for licenses filed by the Southern California Edison Company, San Diego Gas and Electric Company. the City of Riverside, California add the City of Anaheim, California (the licensees), as amended, 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 3 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-98 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:

  • 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. 176

F. The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. 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-15, 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 I. 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, and the Initial Decision issued by the Atomic Safety and Licensing Board on May 14, 1982 regarding this facility, Facility Operating License No. NPF-15 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 3, 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 amended, through Amendment 30, and the Environmental Report, as amended, through Amendment 6.

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 purposes of its retained interests and liabilities.

Amendment No. 223

(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. 228, 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. 228

(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 #5)

Deleted by Amendment No. 26 (5) Environmental Qualification (Section 3.11. SER. SSER #3. SSER #4)

Deleted by Amendment No. 49 (6) High Burnup Fission Gas Release (Section 4.2.2.2. SER)

Deleted by Amendment No. 176 (7) Low Temperature Overpressurization Protection (Section 5.2.2.2. SER)

Deleted by Amendment No. 176 (8) Volume Control Tank Control Logic (Section 7.3.5. SSER #4)

Deleted by Amendment No. 176 (9) Compliance with Regulatory Guide 1.97 (Section 7.5.1. SER. SSER #5)

Deleted by Amendment No. 176 (10) Control System Failures (Section 7.7. SER. SSER #4)

Deleted by Amendment No. 176 (11) Diesel Generator Modifications (Section 8.3.1. SER)

Deleted by Amendment No. 176 (12) Deleted

  • 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. 223

(13) Turbine Disc Inspection (Section 10.2.2. SER)

Deleted by Amendment No. 176 (14) Radioactive Waste System (Section 11.1. SER. SSER #5)

Deleted by Amendment No. 176 (15) Purge System Monitors (Section 11.3. SER. SSER #5)

Deleted by Amendment No. 176 (16) Initial Test Program (Section 14. SER)

Deleted by Amendment No. 176 (17) NUREG-0737 Conditions (Section 22)

Deleted by Amendment No. 176

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

SSER #2. SSER #5)

Deleted by Amendment No. 176

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

Deleted by Amendment No. 176

c. Control Room Design Review (l.D.1. SSER #1)

Deleted by Amendment No. 176

d. Post Accident Sampling System (NUREG-0737 Item 11.B.3)

Deleted by Amendment No. 169

e. Direct Indication of Safety Valve Position (11.D.3. SSER #1)

Deleted by Amendment No. 176

f. AFW Pump 48-hour Endurance Test (11.E.1.1. SSER #11)

Deleted by Amendment No. 176

g. *Emergency Power Supply for Pressurizer Heaters (11.E.3.1.

SSER #1. SSER #5)

Deleted by Amendment No. 176

h. ICC Instrumentation (11.F.2. SSER #1. SSER #2. SSER #4)

Deleted by Amendment No. 176 Amendment No. 223

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

Deleted by Amendment No. 176

j. Improving Licensee Emergency Preparedness (III.A.2, SSER #1, SSER #5)

Deleted by Amendment No. 176 (18) Emergency Preparedness Conditions Deleted by Amendment Nos. 8 and 176 (19) RCS Depressurization System (PORV's)

Deleted by Amendment No. 176 (20) Qualification of Auxiliary Feedwater (AFW) Pump Motor Bearings Deleted by Amendment No. 176 (21) Surveillance Program (Section 1.12, SSER #5)

Deleted by Amendment No. 176 (22) Auxiliary Building Ventilation System.

Deleted by Amendment No. 176 (23) Fuel Assembly Shoulder Gap Clearance (SCE letter of July 25, 1983)

Deleted by Amendment No. 176 (24) Isolation Capability for Primary EOF Deleted by Amendment No. 176 (25) Correction of CPC Software Error Deleted by Amendment No. 176 (26) Reporting of AFWS Failures Deleted by Amendment No. 176 Amendment No. 176 Revised by letter dated July 26, 2007 l

(27) 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
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 (28) Deleted (29) Prior to February 16, 2021, if all spent fuel has not been removed from the Unit 3 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 3 until such time that all spent fuel has been removed from the Unit 3 spent fuel pool.

D. Exemptions to certain requirements of Appendices G, H and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Amendment No. 223

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.

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.

Pursuant to NRC's Order EA-13-092, dated June 5, 2013, NRC reviewed and approved the license amendment 225 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.

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Amendment No. 228

J. Deleted K. Deleted by Amendment No. 176

3. On June 12, 2013, Southern California Edison (SCE) certified that operations at San Onofre Nuclear Generating Station Unit 3 would permanently cease in accordance with 10 CFR 50.82(a)(1)(i). On June 28, 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 10 CFR 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 3 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 REGULATORY COMMISSION Original Signed by Harold R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:

1. Attachment 1 - Deleted by Amendment No. 176
2. Appendix A (Technical Specifications)
3. Appendix B (Environmental Protection Plan)
4. Appendix C (Antitrust Conditions)

Date of Issuance: NOV 15 1982 Amendment No. 223

Appendix A: Technical Specifications San Onofre Unit 3 uses the same Appendix A as San Onofre Unit 2.

Please refer to San Onofre Unit 2 for Appendix A (ML053130316).

DO NOT REMOVE LICENSE AUTHORITY FftE CoPy wi'h 5% A xeAsue Power-7Te6 4i L7 centj APPENDIX B TO FACILITY LICENSE NO. NPF-15 FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 3 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS.AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA AND THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 ENVIRONMENTAL PROTECTION PLAN NOVEMBER 1982

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 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 .......................... a ............ 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-L 4.1 Unusual or Important Environmental Events . . 4-l 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.

K>

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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.

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Protection will be provided through a data recovery program. NRC requirements with regard to the cultural resources issue are specified in Subsection 4.2.1 of this EPP.

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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.

t! 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 operition and of tests and experiments carried out pursuant to this subsection. The!se 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.

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

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3.2 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 agehcy:

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 followingI the date the change is approved.

Ifa permit or certification, inpart or inits entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

3.3 Changes Required for Compliance with Other Environmental Regulations I

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 in significant environmental impact causally related to station operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report within 30 days. No routine monitoring programs are required to implement this condition.

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

Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection. The NRC shall be provided a copy of such report as soon as practical but no later than 30 days after 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.

4.2 Environmental Protection Program 4.2.1 Cultural Resources Data Recovery Program Fourteen archeological sites have been identified within the San Onofre 230 kY 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 4-1 159

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 "1no 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-496, 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.

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