ML080350576
| ML080350576 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/11/2008 |
| From: | Kalyanam N NRC/NRR/ADRO/DORL/LPLIV |
| To: | Rosenblum R Southern California Edison Co |
| Kalyanam N, NRR/DORL/LPL4, 415-1480 | |
| References | |
| TAC MD6835 | |
| Download: ML080350576 (5) | |
Text
February 11, 2008 Mr. Richard M. Rosenblum 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 - REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST FOR ONE-TIME EXTENSION FROM THE CURRENTLY APPROVED 15-YEAR INTERVAL SINCE THE LAST INTEGRATED LEAK RATE TEST (TAC NO. MD6835)
Dear Mr. Rosenblum:
By letter dated September 24, 2007 (Agencywide Documents Access and Management System Accession No. ML072681094), Southern California Edison (the licensee) submitted an application requesting for a one-time extension from the currently approved 15-year interval since the last Integrated Leak Rate Test (ILRT) to a 16-year interval since the last ILRT for the San Onofre Nuclear Generating Station, Unit 3.
After reviewing your request, the Nuclear Regulatory Commission staff has determined that additional information outlined in the enclosure is needed to complete the review. We discussed this information with your staff by telephone and they agreed to provide the additional information requested within 30 days of the receipt of this letter.
If you have any questions, please contact me at (301) 415-1480.
Sincerely,
/RA/
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-362
Enclosure:
Request for Additional Information cc w/encl: See next page
ML080350576 NRR-088
(*)No major change from Staff-provided RAI OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DE/EMCB*
NRR/LPL4/BC NAME NKalyanam:sp JBurkhardt KManoly (*)
THiltz DATE 2/8/08 2/7/08 2/2/08 2/11/08
San Onofre Nuclear Generating Station (December 2007)
Units 2 and 3 cc:
Douglas K. Porter, Esquire Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770 Dr. David Spath, Chief Division of Drinking Water and Environmental Management California Dept. of Health Services 850 Marina Parkway, Bldg P, 2nd Floor Richmond, CA 94804 Chairman, Board of Supervisors County of San Diego 1600 Pacific Highway, Room 335 San Diego, CA 92101 Mark L. Parsons Deputy City Attorney City of Riverside 3900 Main Street Riverside, CA 92522 Mr. Gary L. Nolff Assistant General Manager - Resources Riverside Public Utilities City of Riverside, California 3901 Orange Street Riverside, CA 92501 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Mr. Michael L. De Marco San Diego Gas & Electric Company 8315 Century Park Ct. CP21G San Diego, CA 92123-1548 Resident Inspector San Onofre Nuclear Generating Station c/o U.S. Nuclear Regulatory Commission Post Office Box 4329 San Clemente, CA 92674 Mayor City of San Clemente 100 Avenida Presidio San Clemente, CA 92672 Mr. James T. Reilly Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 Mr. James D. Boyd California State Liaison Officer Vice Chair and Commissioner California Energy Commission 1516 Ninth Street, MS 31 Sacramento, CA 95814 Mr. Gary Butner Acting Branch Chief Department of Public Health Services Radiologic Health Branch MS 7610, P.O. Box 997414 Sacramento, CA 95899-7414 Mr. Ross T. Ridenoure Vice President and Site Manager Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 Mr. A. Edward Scherer Director, Nuclear Regulatory Affairs Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
REQUEST FOR ADDITIONAL INFORMATION SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 TECHNICAL SPECIFICATIONS CHANGES FOR EXTENSION OF THE 15-YEAR INTERVAL FOR THE INTEGRATED LEAK RATE TEST TO A 16-YEAR INTERVAL DOCKET NO. 50-362
- 1.
The U.S. Nuclear Regulatory Commission (NRC) staffs review of the Southern California Edison (the licensee) letter dated September 24, 2007, indicates that refueling outage (RFO)16 will end in the first quarter of 2011. In Technical Specification Section 5.5.2.15, you are requesting to change the integrated leak rate test (ILRT) date to September 9, 2011. The staff notes that you do not need more than a 7-month extension (April 2011). Please clarify the intent of requesting a 1-year extension for performing the next ILRT.
- 2.
For the San Onofre Nuclear Generating Station, Unit 3 (SONGS 3) containment, leak-tight integrity is provided by the metallic liner and structural integrity is provided by the post-tensioned concrete structure. Containment structural integrity is essential to ensuring its leak-tight integrity. If the post-repair containment pressure (integrity) test and the next periodic ILRT are to be performed in combination during RFO 16, please outline the main characteristics of the pressurization process and the extended surface examinations, additional examinations during pressurization, and measurements of structural response to pressure of the affected areas/components of the post-repair containment structure, required by subsection IWL-5250 of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), that SONGS Unit 3 plans to conduct during the combined test. Also, please address how these examinations and the ILRT will be relatively scheduled/sequenced during the combined test.
- 3.
In order to create the containment construction openings (breach) required to facilitate steam generator (SG) replacement, the staff understands that a significant number of the tendons will be removed/de-tensioned and then reinstalled/re-tensioned after completion of SG replacement. Please identify the governing code and/or criteria for SONGS Unit 3's inspection program following the post-tensioning system repair/replacement activity for examination of tendons that will be affected by such major repair/replacement activity. The use of the process established in Subsection IWL-2521.2 of ASME Code,Section XI, 2002 Addenda has been accepted by the NRC in Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR).