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Initiation
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MONTHYEARML12118A1392012-04-20020 April 2012 Units 2 & 3 Components, Portions Outside of Scope Project stage: Request ML12285A2672012-10-0101 October 2012 Attachment 4: SG Tube Wear Analysis for Unit-2/3 Project stage: Request ML12285A2652012-10-0101 October 2012 Attachment 4 - MHI Document L5-04GA564 - Tube Wear of Unit-3 RSG, Technical Evaluation Report Project stage: Request ML12285A2662012-10-0101 October 2012 Attachment 4: Appendix-2 Attachment-1, Tube-to-TSP Wear Depth Diagram for Unit-2/3 Project stage: Request ML12285A2642012-10-0101 October 2012 Attachment 3 - Areva Document 51-9180143-001 - SONGS Unit 3 February 2012 Leaker Outage Steam Generator Condition Monitoring Report Project stage: Request ML12285A2682012-10-0202 October 2012 Attachment 6 - Appendix B: SONGS U2C17 - Steam Generator Operational Assessment for Tube-to-Tube Wear Project stage: Request ML12285A2692012-10-0202 October 2012 Attachment 6: Appendix a: Estimates of FEI-Induced Ttw Rates Project stage: Request ML12285A2632012-10-0303 October 2012 Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation Project stage: Request ML12335A2972012-11-28028 November 2012 LTR-12-0728 - Ltr. Ricardo Nicol Concerns Restart of San Onofre Nuclear Generating Station Project stage: Request ML12338A1102012-11-30030 November 2012 Email, Request for Additional Information Southern California Edisons Response to NRCs Confirmatory Action Letter (CAL) 4-12-001 Dated March 27, 2012 Project stage: RAI ML12341A1122012-12-0707 December 2012 Notice of Meeting with Southern California Edison to Discuss Its Response to NRCs Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2 Project stage: Meeting ML12347A0662012-12-0707 December 2012 Revised Notice of 12/18/12 Meeting with Southern California Edison to Discuss Its Response to NRCs Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2 Project stage: Meeting ML12345A4272012-12-10010 December 2012 Revised Email, Request for Additional Information Review of Southern California Edisons Response to NRCs 3/27/2012 Confirmatory Action Letter (CAL) 4-12-001 and Return to Service Report Project stage: RAI ML12353A0972012-12-13013 December 2012 LTR-12-0795 - 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Cover Through Page 227 of 415 Project stage: Other ML13051A1902013-02-18018 February 2013 Supplemental Document Submittal Regarding Confirmatory Action Letter Response to Address Steam Generator Tube Degradation Project stage: Supplement ML13051A1922013-02-18018 February 2013 Enclosure 4, L5-04GA567, Rev. 6, Evaluation of Stability Ratio for Return to Service Project stage: Other ML13051A1932013-02-18018 February 2013 Enclosure 5, L5-04GA585, Rev. 2, Analytical Evaluations for Operational Assessment Project stage: Other ML13056A0922013-02-20020 February 2013 Email, Draft Request for Additional Information Nos. 38-52, Southern California Edisons Response to NRCs Confirmatory Action Letter Project stage: Draft RAI ML13053A1842013-02-21021 February 2013 Draft Request for Additional Information, Nos. 53-67, Southern California Edisons Response to NRCs Confirmatory Action Letter Project stage: Draft RAI ML13053A1732013-02-21021 February 2013 Email, Draft Request for Additional Information, Nos. 53-67, Southern California Edisons Response to NRCs Confirmatory Action Letter Project stage: Draft RAI ML13056A6012013-02-25025 February 2013 Response to Request for Additional Information (RAI 32) Regarding Confirmatory Action Letter Response Project stage: Response to RAI 2013-01-21
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Text
An EDISON INTERNAT/oNAL Company U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-361 May 16, 2013 Douglas R. Bauder Site Vice President & Station Manager San Onofre Nuclear Generating Station 10 CFR 50.90 Supplement 2 to Amendment Application Number 263 Steam Generator Program San Onofre Nuclear Generating Station, Unit 2
Reference:
Letter from Mr. Peter T. Dietrich (SCE) to NRC dated April 5, 2013, Docket No. 50-361, Amendment Application Number 263 Steam Generator Program, San Onofre Nuclear Generating Station, Unit 2
Dear Sir or Madam:
By letter dated April 5, 2013, Southern California Edison (SCE) submitted Amendment Application No. 263 to Docket No. 50-361 (Reference). The Amendment Application, in part would limit SONGS Unit 2 to a maximum power level of 70% Rated Thermal Power (RTP) for Cycle 17 operation. Two surveillances that would need to be administratively controlled for the duration of Cycle 17 to support the proposed License Amendment were identified in the Amendment Application.
During a phone conversation on April 29, 2013, (ML13122A145), the NRC requested information on how control of these two surveillances would be maintained. To resolve this issue, SCE proposes a license condition to describe the administrative controls for those two Surveillance Requirements.
The proposed License Condition is:
"For Cycle 17 operation, performance of Technical Specification Surveillance Requirements 3.3.1.2 and 3.3.1.5 shall be controlled as follows:
- a. Technical Specification Surveillance Requirement 3.3.1.2 shall be performed with a specified frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This frequency is modified such that the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 2: 68% RTP.
P.O. Box 128 San Clemente. CA 92672 (949) 368-9275 PAX 89275 Fax: (949) 368-9881 Doug.Bauder@sce.com
Document Control Desk May 16, 2013
- b. Technical Specification Surveillance Requirement 3.3.1.5 shall be performed with a specified frequency of 31 days. This frequency is modified such that the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER;::: 68% RTP."
The result of this proposed License Condition is that these two Surveillances will be performed consistent with the current Technical Specification frequency, with the exception that the threshold for initial performance will be following THERMAL POWER exceeding 68% RATED THERMAL POWER (RTP), rather than 85% RTP.
This supplement does not change the scope of the Reference 1 License Amendment Request nor does it change the conclusions of the associated No Significant Hazards Consideration.
There are no regulatory commitments made in this letter.
Should you have any questions, or require additional information, please contact Mr. Mark Morgan, Licensing Lead, at (949) 368-6745.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ? (I b (2-D I>
Sincerely, cc:
A. T. Howell III, Regional Administrator, NRC Region IV R. Hall, NRC Project Manager, SONGS Units 2 and 3 B. Benney, NRC Project Manager, SONGS Units 2 and 3 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 S. Y. Hsu, California Department of Public Health, Radiologic Health Branch