ML083050122

Request for Additional Information Regarding the License Amendment Request to Support Replacement Steam Generators

ML083050122
Person / Time
Site:	San Onofre
Issue date:	11/04/2008
From:	Kalyanam N Plant Licensing Branch IV
To:	Ridenoure R Southern California Edison Co
Kalyanam N, NRR/DLPM, 415-1480
References
TAC MD9160, TAC MD9161
Download: ML083050122 (5)

Text

November 4, 2008 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, UNITS 2 AND 3 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO SUPPORT REPLACEMENT STEAM GENERATORS (TAC NOS. IVID9160 & MD9161)

Dear Mr. Ridenoure:

By letter dated June 27, 2008 to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System (ADAMS) Accession No. ML081830421), Southern California Edison (the licensee) requested an amendment to the San Onofre Nuclear Generating Station, Units 2 and 3, Facility Operating Licenses and Technical Specifications (TS). The proposed changes are in support of the replacement steam generators (SGs) and reflect revised SG inspection and repair criteria and revised peak containment post-accident pressure resulting from installation of the replacement SGs.

The NRC staff has reviewed your submittal and determined that additional information is needed to complete the review. We discussed the need for the enclosed request for additional information with your staff by telephone and they agreed to provide a response within 30 days from the receipt of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If you have any questions, please contact me at (301) 415-1480.

Sincerely, IRAI N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362

Enclosure:

As stated cc w/encl: See next page RidsNrrDorlDpr RidsNrrPMNKalyanam RidsNrrDorlLpl4 RidsOgcRp RidsNrrLAGLappert RidsRgn4MailCenter (CPaulk)

Mr. Ross 1. 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 STATIO UNITS 2 AND 3 REQUEST FOR ADDITIONAL INFORMATION R ARDING THE LICENSE AMENDMENT REQUEST TO SUPPORT REPL CEMENT STEAM GENERATORS (TAC NOS. MD9160 AND M 161)

Dear Mr. Ridenoure:

By letter dated June 27, 2008 (Agencywide Documen Access and a gement System (ADAMS) Accession No. ML081830421), Southern lifornia Edison e licensee) requested an amendment to the San Onofre Nuclear Gener ng Station, Un' and 3, Facility Operating Licenses and Technical Specifications TS). Th~ P s d changes are in support of the replacement steam generators (SGs) an reflect r; vise inspection and repair criteria and revised peak containment post-ac Ident pre r suiting from installation of the replacement SGs.

The U.S. Nuclear Regulatory Commissio (NRC) staff has reviewed your submittal and determined that the additional informatia is needed to complete the review. We discussed the need for the enclosed request for ditional information with your staff by telephone and they agreed to provide a response wi in 30 days from the receipt of this letter.

The NRC staff considers that timel responses to requests for additional information help ensure sufficient time is available or staff review and contribute toward the NRC's goal of efficient and effective use of sta resources. If you have any questions, please contact me at (301) 415-1480.

Sincerely, N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 4, 2008 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, UNITS 2 AND 3 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO SUPPORT REPLACEMENT STEAM GENERATORS (TAC NOS. MD9160 AND MD9161)

Dear Mr. Ridenoure:

By letter dated June 27, 2008 to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System (ADAMS) Accession No. ML081830421), Southern California Edison (the licensee) requested an amendment to the San Onofre Nuclear Generating Station, Units 2 and 3, Facility Operating Licenses and Technical Specifications (TS). The proposed changes are in support of the replacement steam generators (SGs) and reflect revised SG inspection and repair criteria and revised peak containment post-accident pressure resulting from installation of the replacement SGs.

The NRC staff has reviewed your submittal and determined that additional information is needed to complete the review. We discussed the need for the enclosed request for additional information with your staff by telephone and they agreed to provide a response within 30 days from the receipt of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If you have any questions, please contact me at (301) 415-1480.

Sincerely,

~~

N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362

Enclosure:

As stated cc w/encl: See next page

REQUEST FOR ADDITIONAL INFORMATION (RAil SOUTHERN CALIFORNIA EDISON SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362 TAC NOS. MD9160 AND MD9161 By letter dated June 27, 2008 to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System (ADAMS) Accession No. ML081830421), Southern California Edison (the licensee) submitted a license amendment request (LAR) to the San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS 2 and 3). The proposed changes are in support of the replacement steam generators (RSGs) and reflect revised steam generators (SGs) inspection and repair criteria and revised peak containment post-accident pressure resulting from installation of the replacement SGs.

The NRC staff has reviewed your submittal and determined that the following additional information is needed to complete the review:

1. It was stated in Section 3.0 of the enclosure to the LAR that the containment post-accident pressure, mass and energy analyses for the design basis loss-of-coolant accident (LOCA) and main steam line break (MSLB) used the existing methodology while accounting for the differences between the RSGs and the existing SGs.

Section 4.2.1.2 mentions examples of the differences such as greater water volume, higher secondary side operating pressure, greater heat transfer area and larger metal mass. Please quantify the differences between the RSG and the existing SG to the extent they were used in the analyses.

2. Section 4.2.3.1 states that the methodology used in the new evaluation is identical to the methodology used in the current licensing basis evaluation of the SONGS 2 and 3, and that only input parameters have been updated. Other than input parameter changes required by the differences between the RSGs and existing SGs (as would be included in the response to the RAJ above), what other input parameters have been updated and why are they updated? Please explain how the updated parameters are still expected to yield conservative results?

3. Tables 4.2-1 and 4.2-3 provided a summary of significant inputs, significant points of methodology, and assumptions for LOCA and MSLB respectively. Please indicate if all of them are the same between the existing and new analyses with the exception of differences dictated by the SG change out, and if they are different, explain the reasons for the difference and how they would still provide conservative results.

4. Section 4.2.3.2.1, Page 14 of 40 - In the statement, "Although test data indicate that significant condensation of steam occurs at the safety injection location, the model accounts for only 50 percent condensation during the interval when the annulus is predicted to be full and the SITs [safety injection tanks] are injecting. No credit is taken for condensation at the safety injection location at other times," please explain what is the test data that indicates significantly more than 50 percent condensation occurs at the safety injection location?

San Onofre Nuclear Generating Station Units 2 and 3 cc:

Douglas K. Porter, Esquire Mayor Southern California Edison Company City of San Clemente 2244 Walnut Grove Avenue 100 Avenida Presidio Rosemead, CA 91770 San Clemente, CA 92672 Dr. David Spath, Chief Mr. James T. Reilly Division of Drinking Water and Southern California Edison Company Environmental Management San Onofre Nuclear Generating Station California Dept. of Health Services P.O. Box 128 850 Marina Parkway, Bldg P, 2nd Floor San Clemente, CA 92674-0128 Richmond, CA 94804 Mr. Ross T. Ridenoure Chairman, Board of Supervisors Vice President and Site Manager County of San Diego Southern California Edison Company 1600 Pacific Highway, Room 335 San Onofre Nuclear Generating Station San Diego, CA 92101 P.O. Box 128 San Clemente, CA 92674-0128 Mark L. Parsons Deputy City Attorney City of Riverside 3900 Main Street Riverside, CA 92522 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Additional Distribution via Listserv