ML020870205

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Amendment No. 185 Deletion of Completed License Conditions (Tac Nos MB1552 and MB1553)
ML020870205
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 03/27/2002
From:
NRC/NRR/DLPM/LPD4
To:
Southern California Edison Co
References
TAC MB1552
Download: ML020870205 (9)
v • d • e


Text

UNITED STATES 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. 50-361 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 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. 185

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 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 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, use, and operate the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; Amendment No. 185

(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, 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 neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (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. Transshipment of Unit 1 fuel between Units I and 2 shall be in accordance with SCE letters to U.S. Nuclear Regulatory Commission dated March 11, March 18 and March 23, 1988, and in accordance with the Quality Assurance requirements of 10 CFR Part 71.

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 all 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) Maximum Power Level Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. , are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 185

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

(4) r-tainment Tendon Surveillance (Section* 3.8.1, SER, SSER Deleted by Amendment No. 37 (5) Environmental Qualification (Section 3.11, SER, SSER #3, SSER

  1. 4)

Deleted by Amendment No. 60 I (6) High Burnup Fission Gas Release (Section 4.2.2.2. SER)

Deleted by Amendment No. 1 (7) Low Temperature Overpressurization Protection (Section 5.2.2.2. SER)

Deleted by Amendment No. I (8) Control Room Pressurization Capability (Section 6.4, SER, SSER #5)

Deleted by Amendment No. f (9) Seismic Trip System (Section 7.2.5, SSER #4)

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

Deleted by Amendment No. 1 (11) Compliance SSER #5) with Regulatory Guide 1.97 (Section 7.5.1. SER. '

Deleted by Amendment No.

(12) Control System Failures (Section 7.7, SSER #4)

Deleted by Amendment No.

(13) Diesel Generator Modifications (Section 8.3.1, SER)

Deleted by Amendment No.

  • 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

(14) Fire Protection (Section 9.5.1, SER, SSER #4, SSER #5.

1 1.2 SSER #5- SE dated November 15, 1982; Revision 1 to Updated Fire Hazards Analysis Evaluation dated June 29, 1988)

SCE shall implement and maintain in effect all provisions of the approved fire protection program. This program shall be (1) as described in the Updated Fire Hazards Analysis through Revision 3 as revised by letters to the NRC dated May 31, July 22, and November 20, 1987 and January 21, February 22, and April 21, 1988; and (2) as approved in the NRC staff's Safety Evaluation Report (SER) (NUREG-0712) dated February 1981: Supplements 4 and 5 to the SER, dated January 1982 and February 1982, respectively; and the safety evaluation dated November 15, 1982: as supplemented and amended by the Updated Fire Hazards Analysis Eval uation for San Onofre 2 and 3, Revision 1 dated June 29, 1988. SCE may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(15) Turbine Disc Inspection (Section 10.2.2, SER)

Deleted by Amendment No.

(16) Radioactive Waste System (Section 11.1, SER, SSER #5)

Deleted by Amendment No.

(17) Purge System Monitors (Section 11.3. SER. SSER #5)

DelIeted. by 'Amendment.No.

(18) Initial Test Program (Section 14, SER)

Deleted -by Amendment No'.

(19) NUREG-0737 Conditions (Section 22)

Deleted by Amendment.. No...

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

DelSeted by Amaendment. No.

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

Delete~d.:by Amendment No. 147

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

Deleted by Amendment:1No.

d. Procedures for Transients and Accidents (I.C.I. SSER #1, SSER #2, SSER #5)

Deletedby Amendment No.

Amendment No. 185

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

Deleted byAnendment No.

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

Deleted by Amendment No.

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

Deleted by Amendment N.

h. Reactor Coolant System Vents (II.B .1), SSER #1 SSER L4) i.i Deleted by Amendment No.
i. Post-Accident Sampling SYstem (NUREG-0737 Item lILB3)

Deleted by Amendment No. 178

j. Safety Valve Test Requirements (II.D.l. SSER #1)

Deleted: by AmendmenttNo.

k Direct Indication of Safety Valve Position (II.D.3, SSER Eli Deleted by Amendment No.

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

Deleted by Amendment. NNo.

m. Emergency Power Supply for Pressurizer Heaters (II.E.3.1. SSER #1. SSER #5)

Deleted by Amendment No.l

n. Additional Accident Monitoring Instrumentation (II.F.l, SSER #i SSER #4)

Deleted by Amendment No.

o. ICC Instrumentation (II.F.2, SSER #1, SSER #2, SSER #4)
p. Voidinq in the Reactor Coolant System (II.K.2.17, SSER
  1. 1. SSER #5)

Deleted by Amendment No.

q. Revised Model for Small-Break LOCAs (II.K.3.30, SSER #1, SSER #4. SSER #5 Deleted by Amendment No. A Amendment No. 185

-7

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

Deleted by Amendment NoI

s. Improving Licensee Emerqency Preparedness (III.A.2, SSER#1, SSER #5)

Deleted by Amendment No.

(20) Surveillance Program (Section 1.12, SSER #5)

Deleted by Amendment No.

(21) Laboratory Instrumentation (Section 1.12, SSER #5)

Deleted Iy Amendment. No...

(22) Design Verification Program (Section 3.7.4. SSER #5)

Deleted by Amendment, No.

(23) Emergency Preparedness Conditions Deleted- by Amendment, No..

(24) RCS Depressurization System (PORV's)

Deleted by Amendment No.

(25) Qualification of Auxiliary Feedwater (AFW) Pump Motor Bearings Deleted by Amendment No.

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 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. 185

E. SCE shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard 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 plans, which may contain Safeguards Information protected under 10 CFR 73.21, are entitled: "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with revisions submitted through April 22, 1988; "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan," with revisions submitted through October 22, 1986: and "San Onofre Nuclear Generating Station, Units 1, 2, and 3, *Safeguards Contingency Plan," with revisions submitted through December 29, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

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. SCE shall report any violations of the requirements contained in Section 2, items C(1), C(3), and F of this license within 24:hours by telephone and confirm by telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region IV, or his designee, no later than the first working day following the violation, with a written followup report within fourteen (14) days.

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.

Amendment No. 185

J. This license is effective as of the date of issuance and shall expire at midnight on February 16, 2022.

FOR THE NUCLEAR REGULATORY 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 (Environmental Protection Plan)
3. Appendix C (Antitrust Conditions)

Date of Issuance: FEB 16 1982 Amendment No. 185

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