ML110130412

Request for Information for EPU Review

ML110130412
Person / Time
Site:	Saint Lucie
Issue date:	01/13/2011
From:	Orf T Plant Licensing Branch II
To:	Wasik C Florida Power & Light Co
Orf, T J, NRR/DORL/301-415-2788
References
Download: ML110130412 (2)

Text

From: Orf, Tracy Sent: Thursday, January 13, 2011 1:41 PM To: 'Wasik, Chris' Cc: Poehler, Jeffrey; Broaddus, Doug

Subject:

Requested St. Lucie 1 EPU Information

Chris, The revised information request from todays phone call is discussed below. From our discussion today, the NRC staff understands that FPL tentatively plans to submit an exemption request related to the use of the CE NPSD-683-A methodology within approximately 6 weeks.

In the exemption request, FPL will provide responses to the supplemental information questions listed in CD NPSD-683-A and/or identify which questions do not apply in this case. Additionally, a tabulation of the KIT and KIM factors will be submitted by FPL as a supplement to the EPU LAR.

Please let me know if you need additional clarification or discussion on this, or if I have misstated something in my summary above.

Best regards, Trace Tracy J. Orf, Project Manager St. Lucie Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Phone: (301) 415-2788 WCAP-17197-NP, Rev. 0, St. Lucie Unit 1 RCS Pressure and Temperature Limits and Low-Temperature Overpressure Protection Report for 54 Effective Full Power Years, provides the basis for the revised pressure-temperature (P-T) limits for St. Lucie Unit 1 incorporating revised fluence values that account for the extended power uprate (EPU). Figures 3.4-2a and 3.4-2b of the technical specifications have been revised to incorporate the new P-T limits.

As part of the calculation of the revised P-T limits, to determine the thermal stress intensity factors (KIt) and membrane stress intensity factors (KIm) through the RV wall, the applicant used the method of CE NPSD-683-A (Reference 1), rather than the method described in the ASME Code Section XI, Appendix G, paragraph G-2214.3. The staff has approved CE NPSD-683-A via a safety evaluation (SE, included at the beginning of Reference 1), which required a number of information items to be included in plant-specific submittals referencing the CE NPSD-683-A methodology. A finite element method was used in Reference 1 to generate the KIm and KIt factors, which are inputs to the allowable pressure. The method of generating the KIm and KIt factors was different and could not be shown to be equally conservative as the methods of the ASME Code Section XI, Appendix G, as required by 10 CFR 50.60, Acceptance Criteria For Fracture Prevention Measures For Lightwater Nuclear Power Reactors For Normal Operation, and 10 CFR 50 Appendix G. Therefore, Information Item #21 in Section 5.0 of the SE requires applicants using the methods of CE NPSD-683-A to calculate the KIm and

KIt factors used to generate the P-T limits to submit a plant-specific exemption request in accordance with 10 CFR 50.12, Specific Exemptions.

Requested Information

1. Submit an exemption request pursuant to 10 CFR 50.12 to allow the use of the CE NPSD-683-A methodology to generate the KIm and KIt factors used to generate the P-T limits, and;

2. Provide a tabulation of the KIt and KIm values used to generate the P-T limits.

References

1. Westinghouse Report, CE-NPSD-683-A Task-1174, Revision 06, Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP equirements from the Technical Specifications, April 2001 (ADAMS Accession No. ML0113503871)