L-PI-03-098, Application of Leak-Before-Break Technology to Replacement Steam Generator Design

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Application of Leak-Before-Break Technology to Replacement Steam Generator Design
ML033320057
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 11/18/2003
From: Solymossy J
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-03-098, TAC MB7509
Download: ML033320057 (2)


Text

N M C]

~~~~~~~~~Prabb an Nde SCG"Mt abnt ComA Vel Nulwd to Operated by Nuclear Maent Comny, LLC L-Pl03- 098 November 18,2003 10 CFR 60 Appendix A, GDC-4 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET 50-282 LICENSE No. DPR-42 APPLICATION OF LEAK-BEFORE-BREAK TECHNOLOGY TO REPLACEMENT STAM GENERATOR OfIIGN TA NQ. M75091)

By letter dated January 29,2003 the Nuclear Management Company, LLC (NMC) submitted a letter requesting the Nuclear Regulator Commission (NRC) provide confirmation that the replacement steam generators may be designed on the basis of the reduced loads resulting from the application of leak-before-break criteria to postulated breaks In the primary reactor coolant loop piping. In that letter the NMC outlined the licensing justification for designing the replacement steam generators based on the reduced loads. By letter dated April 23, 2003, the NRC identified that additional nformation was needed. In accordance with the request in the NRC's April 23, 2003 letter, the NMC provided the additional information in letter dated June 2, 2003.

Subsequent to the June 2, 2003 letter, the NRC verbally informed the NMC that the NRC would no longer be providing the type of confirmation requested in the January 29, 2003 letter. Therefore the NMC is withdrawing the request that the NRC provide confirmation that the replacement steam generators may be designed on the basis of the reduced loads resulting from the application of leak-before-break criteria to postulated breaks In the primary reactor coolant loop piping.

This letter contains no new commitments and no revisions to existing commitments.

t177 Wakonade Drive East

  • Welch, Minnesota 550899642 Telephone: 651.388.1121 IWYD

USNRC L-PI-03-098 Page 2 NUCLEAR MANAGEMENT COMPANY, LLC Please address any comments or questions regarding this letter to Mr. H Oey Nelson at 1-651-388-1121.

Jose M Solymos S(te ce President, V

land Nuclear Generating Plant CC Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant 1717 Wakonade Dive East

  • Welch, Minnesota 55089-9642 Telephone: 651.388.1121