ML052440304
| ML052440304 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/12/2005 |
| From: | Donohew J NRC/NRR/DLPM/LPD4 |
| To: | Ray H Southern California Edison Co |
| Donohew J N, NRR/DLPM,415-1307 | |
| References | |
| TAC MC3797, TAC MC3798 | |
| Download: ML052440304 (5) | |
Text
Mr. Harold B. Ray September 12, 2005 Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION (SONGS), UNITS 2 AND 3 RE: CORRECTION TO AMENDMENTS ON CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NOS. MC3797 AND MC3798)
Dear Mr. Ray:
In its letter dated August 24, 2005, the Nuclear Regulatory Commission (NRC) staff issued Amendment No.198 to Facility Operating License No. NPF-10 and Amendment No.189 to Facility Operating License No. NPF-15 for San Onofre Nuclear Generating Station (SONGS),
Units 2 and 3, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated June 30, 2004, as supplemented by letters dated December 2, 2004, May 27, and July 18, 2005.
In the safety evaluation (SE) attached to its letter dated August 24, 2005, the NRC staff stated incorrectly that (1) the units are Westinghouse pressurized-water reactors (PWRs) and (2) the next overall verification of the containment leak-tight integrity is proposed to be performed at SONGS Unit 2 by March 20, 2010. The correct statements are the units are Combustion Engineering PWRs and the next overall verification for SONGS Unit 2 is proposed to be performed by March 30, 2010. Neither of these errors were part of the basis for the NRC staff to approve the amendments. To correct these errors, I have enclosed a corrected page 2 of that SE with vertical bars on the right-hand side of the page showing where the corrections were made.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosure:
Page 2 of Safety Evaluation dated August 24, 2005 cc w/encl: See next page
Mr. Harold B. Ray September 12, 2005 Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION (SONGS), UNITS 2 AND 3 RE: CORRECTION TO AMENDMENTS ON CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NOS. MC3797 AND MC3798)
Dear Mr. Ray:
In its letter dated August 24, 2005, the Nuclear Regulatory Commission (NRC) staff issued Amendment No.198 to Facility Operating License No. NPF-10 and Amendment No.189 to Facility Operating License No. NPF-15 for San Onofre Nuclear Generating Station (SONGS),
Units 2 and 3, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated June 30, 2004, as supplemented by letters dated December 2, 2004, May 27, and July 18, 2005.
In the safety evaluation (SE) attached to its letter dated August 24, 2005, the NRC staff stated incorrectly that (1) the units are Westinghouse pressurized-water reactors (PWRs) and (2) the next overall verification of the containment leak-tight integrity is proposed to be performed at SONGS Unit 2 by March 20, 2010. The correct statements are the units are Combustion Engineering PWRs and the next overall verification for SONGS Unit 2 is proposed to be performed by March 30, 2010. Neither of these errors were part of the basis for the NRC staff to approve the amendments. To correct these errors, I have enclosed a corrected page 2 of that SE with vertical bars on the right-hand side of the page showing where the corrections were made.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation DISTRIBUTION Docket Nos. 50-361 and 50-362 PUBLIC PDIV-2 r/f
Enclosure:
Page 2 of Safety Evaluation RidsNrrDlpmLpdiv(HBerkow) dated August 24, 2005 RidsNrrDlpmLpdiv2 RidsNrrPMJDonohew cc w/encl: See next page DCollins RidsNrrLALFeizollahi RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn4MailCenter (TPruett)
RidsNrrDlpmDpr ACCESSION NO: ML052440304 NRR-106 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC(A)
NAME JDonohew LFeizollahi DCollins DATE 09/12/05 09/08/05 09/12/05 OFFICIAL RECORD COPY
method acceptable to the NRC staff for complying with Option B via the use of NEI 94-01 and ANSI/ANS 56.8-1994, subject to applicable regulatory positions documented in RG 1.163.
3.0 TECHNICAL EVALUATION
3.1 Aging Degradation of the Containment Pressure Boundary SONGS, Units 2 and 3 are Combustion Engineering pressurized-water reactors (PWRs) with l large reinforced-concrete primary containment. The containment pressure boundary consists of the steel liner, containment access penetrations, and process piping and electrical penetrations. The integrity of the penetrations is verified through Type B and Type C local leak rate tests (LLRT) as required by 10 CFR Part 50, Appendix J, and the overall integrity of the containment structure is verified through an ILRT. These tests are performed to verify the essentially leak-tight characteristics of the containment structure at the design-basis accident (DBA) pressure. As stated in the licensees June 30, 2004, TS amendment request, the surveillance frequency for Type A testing in NEI 94-01 is once every 10 years based on an acceptable performance history (i.e., two consecutive periodic Type A tests at least 24 months apart where the calculated performance leakage rate was less than 1.0 La) and consideration of the performance factors in NEI 94-01, Section 11.3. Based on the last two consecutive successful ILRT Type A tests (Unit 2 - March 31, 1995, and October 25, 1991; Unit 3 -
September 10, 1995, and March 9, 1992) and the requirements of 10 CFR Part 50, Appendix J, Option B, the current interval for SONGS is once every 10 years for both units. With the requested extension of the ILRT time interval, the licensee proposed that the next overall verification of the containment leak-tight integrity be performed by March 30, 2010, for Unit 2 l and by September 9, 2010, for Unit 3.
Because the leak rate testing requirements (ILRT and LLRT) of Option B of 10 CFR Part 50, Appendix J, and the containment inservice inspection (ISI) requirements mandated by 10 CFR 50.55a complement each other in ensuring the leak-tightness and structural integrity of the containment, the staff, based on its review of Type A test interval extension applications from other licensees, identified the following five general areas to evaluate in relation to the ISI of the containment and requested the licensee to provide information in these areas:
- 1. Since the submittal did not include sufficient description or summary of the containment ISI program being implemented at the plant, the licensee was requested to provide a description of the ISI methods that provides assurance that, in the absence of a containment ILRT for 15 to 20 years, the containment structural and leak-tight integrity will be maintained.
- 2. IWE-1240 of the American Society of Mechanical Engineers (ASME) Code requires licensees to identify the containment surface areas requiring augmented examinations.
The licensee was requested to provide the locations of the steel containment (or concrete containment liner) surfaces that have been identified as requiring augmented examination and a summary of the findings of the examinations performed.
- 3. For the examination of penetration seals and gaskets, and examination and testing of bolted connections associated with the primary containment pressure boundary (Examination Categories E-D and E-G), the licensee requested relief from the
San Onofre Nuclear Generating Station Units 2 and 3 cc:
Mr. Daniel P. Breig, Plant Manager Mr. Ed Bailey, Chief Nuclear Generation Radiologic Health Branch Southern California Edison Company State Department of Health Services San Onofre Nuclear Generating Station Post Office Box 997414 (MS7610)
P. O. Box 128 Sacramento, CA 95899-7414 San Clemente, CA 92674-0128 Resident Inspector/San Onofre NPS Mr. Douglas K. Porter c/o U.S. Nuclear Regulatory Commission Southern California Edison Company Post Office Box 4329 2244 Walnut Grove Avenue San Clemente, CA 92674 Rosemead, CA 91770 Mayor Mr. David Spath, Chief City of San Clemente Division of Drinking Water and 100 Avenida Presidio Environmental Management San Clemente, CA 92672 P. O. Box 942732 Sacramento, CA 94234-7320 Mr. James T. Reilly Southern California Edison Company Chairman, Board of Supervisors San Onofre Nuclear Generating Station County of San Diego P.O. Box 128 1600 Pacific Highway, Room 335 San Clemente, CA 92674-0128 San Diego, CA 92101 Mr. James D. Boyd, Commissioner Eileen M. Teichert, Esq. California Energy Commission Supervising Deputy City Attorney 1516 Ninth Street (MS 31)
City of Riverside Sacramento, CA 95814 3900 Main Street Riverside, CA 92522 Mr. Ray Waldo, Vice President Southern California Edison Company Mr. Gary L. Nolff San Onofre Nuclear Generating Station Power Projects/Contracts Manager P.O. Box 128 Riverside Public Utilities San Clemente, CA 92764-0128 2911 Adams Street Riverside, CA 92504 Mr. Brian Katz Vice President, Nuclear Oversight and Regional Administrator, Region IV Regulatory Affairs.
U.S. Nuclear Regulatory Commission San Onofre Nuclear Generating Station 611 Ryan Plaza Drive, Suite 400 P.O. Box 128 Arlington, TX 76011-8064 San Clemente, CA 92764-0128 Mr. Michael Olson San Diego Gas & Electric Company P.O. Box 1831 San Diego, CA 92112-4150 August 2005
San Onofre Nuclear Generating Station Units 2 and 3 cc:
Mr. Steve Hsu Department of Health Services Radiologic Health Branch MS 7610, P.O. Box 997414 Sacramento, CA 95899