ML17354A732

Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology

ML17354A732
Person / Time
Site:	Turkey Point
Issue date:	12/04/1997
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17354A731	List: ML17354A730 ML17354A732
References
NUDOCS 9712110052
Download: ML17354A732 (2)

Text

Q/ 3. WCAP-10054-P, Westinghouse Addendum 2, Small Break Revision 1 (proprietary), "Addendum to the ECCS Evaluation Model Using the NOTRUMP I

Code: Safety Injection in the Broken Loop and Improved Condensation Model", October 1995.*

4. WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V, June 1996.**

5. USNRC Safety Evaluation Report, Letter from R. C. Jones (USNRC) to N. J. Liparulo.(H), "Acceptance for Referencing of the Topical Report WCAP-12945(P) 'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,'" June 28, 1996.**

6. Letter dated June 13, 1996, from N. J. Liparulo (H) to Frank R. Orr (USNRC), "Re-Analysis Work Plans Using Final Best Estimate Methodology."**

The analytical methods used to determine Rod Bank Insertion Limits and the All Rods Out position shall be th'ose previously reviewed and approved by the NRC in:

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985.

The ability to calculate the COLR nuclear design parameters are demonstrated ln Florida Power & Light Company Topical Report NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point & St. Lucie Nuclear Plants".

Topical Report NF-TR-95-01 was approved by the NRC for use by Florida Power &

Light Company in:

Safety Evaluation by the Office of Nuclear Reactor Regulations Related to Amendment No. 174 to Facility Operating License DPR-31 and Amendment No. 168 to Facility Operating License DPR-41, Florida Power & Light Company Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251.

The AFD, FQ(Z), FzH, K(Z), and Rod Bank Insertion Limits shall be determined such that all applicable limits of the safety analyses are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector, unless otherwise approved by the Commission.

6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office 'of the NRC within the time period specified for each report as 97i2ii0052 97i204%

PDR- =:ADOCK-05000250-.

P POR

• This reference is only to be used subsequent to NRC approval.

• • As evaluated in NRC Safety Evaluation dated TURKEY POINT - UNITS 3 & 4 6-22 AMENDMENT NOS AND

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