ML090480433

Correction to Pages Issued with Amendment No. 210

ML090480433
Person / Time
Site:	San Onofre
Issue date:	02/20/2009
From:	Kalyanam N Plant Licensing Branch IV
To:	Ridenoure R Southern California Edison Co
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC MD6835
Download: ML090480433 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2009 Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 - CORRECTION TO PAGES ISSUED WITH AMENDMENT NO. 210 (TAC NO. MD6835)

Dear Mr. Ridenoure:

On August 15, 2008, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 210 to Facility Operating License No. NPF-15 for the San Onofre Nuclear Generating Station, Unit 3.

While the paper copies of the amended license and technical specification pages correctly showed the amendment number, an administrative error was discovered in the electronic version under Agencywide Documents Access and Management System (ADAMS) Accession No. ML082030733. The error resulted in the omission of amendment numbers on the license and technical specification pages. The administrative error does not change the NRC staff's conclusions in Amendment No. 210.

We have enclosed copies of the corrected license and technical specification pages for this amendment. If you have questions, please contact me at me at 301-415-1480 or by email at kaly.kalyanam@nrc.gov.

Sincerely,

\. /.70~~

~LJ~

N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-362

Enclosure:

As stated cc w/encl: Distribution via Listserv

ENCLOSURE Attachment to License Amendment No. 210, Issued August 15, 2008

ATTACHMENT TO LICENSE AMENDMENT NO. 210 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Facility Operating License No. NPF-15 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Operating License REMOVE INSERT Page 3 Page 3 Technical Specifications REMOVE INSERT 5.0-20a 5.0-20a

-3 (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 materials 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 3 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 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 S, as revised through Amendment No. 210 , 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. 210

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.15 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program", dated September 1995 as modified by the following exception:

NET 94 1995, Section 9.2.3: The first Type A Test performed after the September 10, 1995 Type A Test shall be performed prior to startup from the Unit 3 Cycle 16 refueling outage, which is scheduled to commence in the fall of 2010 and to end in the first quarter of 2011. SONGS Unit 3 shall not operate past September 9, 2011 until the Type A Test is satisfactorily completed.

The calculated peak containment internal pressure related to the design basis loss-of-coolant accident, Pa, is 45.9 psig (P a will conservatively be assumed to be equal to the calculated peak containment internal pressure for the design basis Main Steam Line Break (56.5 psig) for the purpose of containment testing in accordance with this Technical Specification).

The maximum allowable containment leakage rate, La' at Pal shall be 0.10% of containment air weight per day.

Leakage rate acceptance criteria are:

a. The Containment overall leakage rate acceptance criterion is

~ 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are $ 0.60 La for the Type B and Type C tests and

~ 0.75 L. for the Type A tests;

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is ., 0.05 La when tested at ~ Pa *

2) For each door, the leakage rate is $ 0.01 ~ when pressurized to ~ 9.0 psig.

(continued)

SAN ONOFRE--UNTT 3 5.0-20a Amendment No.210

ML090480433 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlLPL4/BC NRRlLPL4/PM NAME NKalyanam JBurkhardt MMarkley NKalyanam DATE 2/20/09 2/20/09 2/20/09 2/20/09