ML100060627
| ML100060627 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/20/2010 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Markley M Plant Licensing Branch IV |
| Hall, J R, NRR/DORL/LPL4, 301-415-4032 | |
| References | |
| TAC ME2340, TAC ME2341 | |
| Download: ML100060627 (4) | |
Text
January 20, 2010 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
James R. Hall, Senior Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE DECEMBER 23, 2009, CONFERENCE CALL WITH SOUTHERN CALIFORNIA EDISON COMPANY REGARDING RELIEF REQUEST ISI-3-30 FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 (TAC NOS. ME2340 AND ME2341)
By letter dated October 2, 2009 (Agencywide Documents Access Management System (ADAMS) Accession No. ML092790155), as supplemented by letter dated December 18, 2009 (ADAMS Accession No. ML093570270), Southern California Edison Company (SCE), the licensee for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, submitted Relief Request ISI-3-30, Inspection of Reactor Vessel Head In-Core Instrument Nozzles, for approval by the staff of the Nuclear Regulatory Commission (NRC). The licensee requested relief from the inspection requirements of American Society of Mechanical Engineers (ASME) Code Case N-729-1, Alternative Examination Requirements for Pressurized Water Reactor (PWR) Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial Penetration Welds,Section XI, Division 1, as required and conditioned by Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50) paragraph 55a(g)(6)(ii)(D) for SONGS, Units 2 and 3.
Specifically, the licensee stated that, due to the inability to qualify the volumetric examination techniques and personnel in accordance with 10 CFR 50.55a(g)(6)(ii)(D)(4), surface examination of the In-Core Instrument (ICI) nozzles to the extent required by Code Case N-729-1 would result in a hardship due to high personnel radiological exposure without a compensating increase in the level of quality or safety, and requested NRC approval of the alternative examination in accordance with 10 CFR 50.55a(a)(3)(ii).
A conference call was held on December 23, 2009, to discuss the results of the NRC staffs review of the relief request with SCE. The NRC Project Manager (PM) noted that SCE had requested approval of ISI-3-30 by December 26, 2009, in order to support the start-up of the Unit 2 reactor upon completion of the current refueling outage. The PM also noted that NRC procedures allow for granting temporary verbal authorizations under 10 CFR 50.55a(a)(3), in certain limited circumstances, as described in LIC-102, Revision 2, Relief Request Reviews, dated August 24, 2009 (ADAMS Accession No. ML091380595). SCE submitted the application in October 2009. The NRC staff has completed its technical review of ISI-3-30; however, due to the limited time between the submittal date and the requested approval date, the staff has not
yet completed its written safety evaluation; therefore, the staff considered this relief request as a candidate for a verbal authorization.
The NRC staff summarized the results of its review of the relief request and stated that it finds that the proposed alternative provides reasonable assurance of structural integrity and leak tightness. The staff also finds that complying with the requirements of ASME Code Case N-729-1, as required and conditioned by 10 CFR 50.55a(g)(6)(ii)(D), would present a significant hardship due to radiological exposure without a compensating increase in the level of quality or safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the use of the proposed alternative for SONGS, Unit 2, is authorized until the 17th refueling outage in the fall of 2011. At that time, SCE plans to replace the Unit 2 reactor vessel head. The replacement head will incorporate design changes such that this relief will no longer be needed. The NRC staffs approval of the alternative examination for the ICI nozzles only applies to Unit 2 at this time.
All other requirements of ASME Code Case N-729-1 and 10 CFR 50.55a(g)(6)(ii)(D) not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC staff stated that it will issue a written safety evaluation in the near future, in support of its authorization for SCE to use the alternative examination described in relief request ISI-3-30.
A list of the participants on the call is enclosed.
Docket Nos. 50-361 and 50-362
Enclosure:
List of Participants
yet completed its written safety evaluation; therefore, the staff considered this relief request as a candidate for a verbal authorization.
The NRC staff summarized the results of its review of the relief request and stated that it finds that the proposed alternative provides reasonable assurance of structural integrity and leak tightness. The staff also finds that complying with the requirements of ASME Code Case N-729-1, as required and conditioned by 10 CFR 50.55a(g)(6)(ii)(D), would present a significant hardship due to radiological exposure without a compensating increase in the level of quality or safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the use of the proposed alternative for SONGS, Unit 2, is authorized until the 17th refueling outage in the fall of 2011. At that time, SCE plans to replace the Unit 2 reactor vessel head. The replacement head will incorporate design changes such that this relief will no longer be needed. The NRC staffs approval of the alternative examination for the ICI nozzles only applies to Unit 2 at this time.
All other requirements of ASME Code Case N-729-1 and 10 CFR 50.55a(g)(6)(ii)(D) not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC staff stated that it will issue a written safety evaluation in the near future, in support of its authorization for SCE to use the alternative examination described in relief request ISI-3-30.
A list of the participants on the call is enclosed.
Docket Nos. 50-361 and 50-362
Enclosure:
List of Participants DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMSanOnofre Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JWallace, NRR/DCI/CPNB JCollins, NRR/DCI/CPNB RLantz, RIV/DRP ADAMS Accession No: ML100060627 OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CPNB/BC NRR/LPL4/BC NRR/LPL4/PM NAME JRHall JBurkhardt TLupold MMarkley JRHall DATE 1/8/10 1/7/10 1/19/10 1/20/10 1/20/10 OFFICIAL AGENCY RECORD
Enclosure LIST OF PARTICIPANTS DECEMBER 23, 2009, CONFERENCE CALL REGARDING RELIEF REQUEST ISI-3-30 FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362 SOUTHERN CALIFORNIA EDISON COMPANY Linda Conklin, Manager, Nuclear Licensing Mark Morgan, Nuclear Licensing U.S. NUCLEAR REGULATORY COMMISSION Terence Chan, Chief, Piping and NDE Branch (CPNB), DCI/NRR Michael Markley, Chief, Plant Licensing Branch IV, DORL/NRR Jay Wallace, CPNB James R. Hall, Senior Project Manager