ML091940108

Correction to Amendment No. 213, Revise Technical Specification Changes in Support of Steam Generator Replacement

ML091940108
Person / Time
Site:	San Onofre
Issue date:	07/17/2009
From:	Hall J Plant Licensing Branch IV
To:	Ridenoure R Southern California Edison Co
Hall, J R, NRR/DORL/LPL4, 301-415-4032
References
TAC MD9161
Download: ML091940108 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 17, 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 AMENDMENT NO. 213 RE: TECHNICAL SPECIFICATION CHANGES IN SUPPORT OF STEAM GENERATOR REPLACEMENT (TAC NO. MD9161)

Dear Mr. Ridenoure:

On June 25, 2009 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML091670298), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 220 to Facility Operating License No. NPF-10 and Amendment No. 213 to Facility Operating License No. NPF-15 for the San Onofre Nuclear Generating Station (SONGS), Units 2, and 3, respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 27,2008, as supplemented by letters dated August 13, 2008, and February 5,2009.

The amendments revised TSs 3.4.17, "Steam Generator (SG) Tube Integrity," 5.5.2.11, "Steam Generator (SG) Program," 5.5.2.15, "Containment Leakage Rate Testing Program," and 5.7.2.c, "Special Reports," in support of the planned replacement of the steam generators at SONGS Units 2 and 3.

The revised TS page 5.0-20a issued with Amendment No. 213 for SONGS Unit 3 inadvertently changed the wording of TS 5.5.2.15 and reversed a change from an earlier amendment.

Amendment No. 210, issued August 15, 2008 (ADAMS Accession No. ML082030707), allowed an exception to the containment integrated leakage test schedule for Unit 3, as specified in the following paragraph:

NEI 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.

Amendment No. 213 inadvertently restored the previous wording for TS 5.5.2.15, which required the next Type A Test for Unit 3 to be performed no later than September 9, 2010.

This administrative error only affected page 5.0-20a of the Unit 3 TSs and did not impact the Amendment No. 220 for Unit 2. The error does not change the staff's conclusions regarding Amendment Nos. 220 and 213 for SONGS Units 2 and 3, respectively. Enclosed is a corrected

R. T. Ridenoure

- 2 version of page 5.0-20a for the SONGS Unit 3 TSs. Please discard the associated page issued with Amendment No. 213 and replace it with the enclosed corrected page.

We apologize for any inconvenience caused by this error. If you have any questions, please call me at 301-415-4032.

Sincerely, l::/~e?a~ect 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 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 LICENSE AMENDMENT NO.

Corrected Technical Specification Page 5.0-20a 213

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 Regul atory Gui de 1.163, "Performance-Based Contai nment Leak-Test Program," dated September 1995 as modified by the following exception:

NEI 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 schedul~d 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, Pao is 48.0 psig (Pa will conservatively be assumed to be equal to the calculated peak containment internal pressure for the design basis Main Steam Line Break (51.5 psig) for the purpose of containment testing in accordance with this Technical Specification).

The maximum allowable containment leakage rate, Lao at Pa, shall be 0.10% of containment air weight per day.

Leakage rate acceptance criteria are:

a.

The Containment overall leakage rate acceptance criterion is 5 1.0 La.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 La for the Type B and Type C tests and 5 0.75 La 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 1eakage rate is:; 0.01 La when pressurized to ~ 9.0 psig.

(continued)

SAN ONOFRE--UNIT 3 5.0-20a Amendment No. 213

R. T. Ridenoure

- 2 version of page 5.0-20a for the SONGS Unit 3 TSs. Please discard the associated page issued with Amendment No. 213 and replace it with the enclosed corrected page.

We apologize for any inconvenience caused by this error. If you have any questions, please call me at 301-415-4032.

Sincerely, IRA!

James R. Hall, Senior 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 DISTRIBUTION:

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