ML17354A477

Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis

ML17354A477
Person / Time
Site:	Turkey Point
Issue date:	04/24/1997
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17354A476	List: L-97-108, Requests That Addl Ref Be Added to Turkey Point,Units 3 & 4 TS Section 6.9.1.7, Colr ML17354A477
References
L-97-108, NUDOCS 9705010343
Download: ML17354A477 (5)

Text

Attachment 2 Page 1 of 3 I 97-108 Proposed Technical Specification Page 6-22 5OOOa5O Pop gDQCK 0 l

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WCAP-10054-P, Addendum 2, Revision I (proprietary),

"Addendum to the gestinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code:

Safety Infection in the Broken Loop and Improved Condensation Model", October 1995.*

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ggggP. t The analytical methods used to deteraine Rod Bank Insertion Limits and the All Rods Out position shall be those previously reviewed and approved by.the NRC in:

1.

WCAP-9272-P-A. "Westinghoust Reload Safety Evaluation Methodology,"

July 1985.

The ability to calculate the COLR nuclear design parameters are demonstrated in:

1.

Florida Power

& Light Company Topical Report NF-TR-95-01, "Nuclear Physics Methodology for Relaad 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:

1.,

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 AFO, FO(2),.F H, K(2>. and Rod Bank Insert(on Llmlts shall be determined such that all. app (cable llmlts of the safety analyses are met.

The CORE

.OPERATING LIMITS REPORT.

Inc1ud(np any m(d-cycle res(s$ ons 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 submftted to the Regional Administrator of the Regional Office of the NRC within the time period specified for eac'h report as stated in the Specifications within Sections 3.0, 4.0, or 5.0.

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

TURKEY POINT - UNITS 3

& 4 6-22 AMENDMENT NOS. 192 ANO

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Atthchment 2 Page 3 of 3 I 97-108 Insert A 4.

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

5.

USNRC Safety Evaluation Report, Letter from R. C. Jones (USNRC) to N. J.

Liparulo QQ, "Acceptance for Referencing of the Topical Report WCAP-12945(P) Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,"'une 28, 1996.

6.

Letter dated June 13, 1996, from N. J. Liparulo QQ to Frank R. Orr (USNRC),

"Re-Analysis Work Plans Using Final Best Estimate Methodology."

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