ML17354A422

Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis

ML17354A422
Person / Time
Site:	Turkey Point
Issue date:	02/24/1997
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17354A421	List: ML17354A420 ML17354A422
References
NUDOCS 9703040221
Download: ML17354A422 (6)

Text

Attachment 3 L-97-037 Page1of4 Proposed Technical Specification Pages 6-21 6-22 970304022i 970224 PDR ADQCK 05000250 P PDR

6.'9.1.6 The W(Z) function(s) for Base-Load Operation corresponding to a +2Z band about the target flux difference and/or a +3K band about the target flux difference, the Load-Follow function Fz(Z) and the augmented surveillance turnon power fraction, P~, shall be provided to the U.S. Nuclear Regulatory Commission, whenever P~ ts cl.0. In the event, the option of Baseload Operation (as defined in Section 4.2.2.3) will not be exercised, the submission of the W(Z) function is not required. Should these values (i.e., W(Z), Fz(Z) and PT) change requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC DoCument Control desk with copies to the Regional Administrator and the Resident Inspector within '30 days of their implementation, unless by the Commission.

otherwise'pproved The analytical Wethods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for review and approval prior to their use if the change is determined to involve an unreviewed safety question or if such a change would require amendment of previously submitted documentation.

6.9. 1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:

1. Axial Flux Difference for Specification 3.2. 1.

2. Control Rod Insertion Limits for Specification 3.1.3.6.

3.. Heat Flux Hot Channel Factor - F0(Z) for Specification 3/4.2.2.

4. All Rods Out position for Specification 3. 1.3.2.

5. 'uclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3 The analytical methods used to determine the AFD limits shall be those .

previously reviewed and approved by the NRC in:

1. WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FO SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.

2. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES-TOPICAL REPORT," September 1974.

The analytical aethods used to determine FO(Z), F>H and the K(Z) curve shall be those previously reviewed and approved by the NRC in:

1. WCAP-9220-P-A, Rev. 1, "Westinghouse ECCS Evaluation Model - 1981 Version," February 1982.

~g f 1- -A, ev 1. "B T -1: f t st QO~ 2 CA ti

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3, Re Com oo Tr ns nts - Sp cia te Rep Co t: i le o 1 i E 5 lu io Mo WCAp-10054-p-A, (proprletarp). "Westinghouse Small Break BCCS Evaluation Model Using the NOTRUMP Code", August 1985.

RG'Pic. E TURKEY POINT - UNITS 3 5 4 6-21 AMENDMENT NOS. 192 AND 186

HCAP -IOO54-P, Addendum 2, Revision I (propr1etary>. "Addendum to the Hest1nghouse Small Break ECCS Evaluation Nodal Us1np the NOTRUHP (Lm(>(Aalu code: safety Inject(on in the Broken Loop and Improved condensation Model", October 1995.*

5 P-10 66- A, R v 2 (prop feta ), a d M P-115 -NP- R v 2 giLt W (n -pro riet ry). "Th 1981 Vers n o the stin ouse CC Eva atfo Nod 1 Us g e SA Co ," N 19 0-N C 143, "Cha e Met dolo for Exec ion o BAS gg5HP.7 The

~ E analytical lua fon del, Hay 3, 4.

methods used to deterafne Rod Bank Insertion Lfmfts and the All Rods Out po'sftfon shall be those previously reviewed and approved by .the NRC fn:

l. WCAP-9272-P-A. "Westinghouse Reload Safety Evaluation Methodology."

July 1985.

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

1. Florida Power 8 Light Company Topical Report NF-TR-95-01, "Nuclear Physics Hethodology for Relaad Design of Turkey Point 8 St. Lucfe Nuclear Plants".

Topical Report NF-TR-95-01 was approved by the NRC for use by Florfda Power 5 Light Company fn:

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 8 Light Company Turkey Point Units 3 and 4, Docket Nos. 50-250 .and 50-251.

The AFO. FO(2>..F H, (((2>, and Rod Bank Insertion Lim1ts shall be determined such that all. app (cable lim1ts of the safety analyses are met. The CORE OPERATING LIHITS REPORT, 1ncluding any m1d-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 Commfssion.

6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC wfthfn the tfme period specified for each report as stated fn the Specifications within Sections 3.0, 4.0, or 5.0.

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

TURKEY POINT - UNITS 3 5 4 6-22 AMENDMENT NOS. 192 AND 186

L-97-037 Page 4of 4 Insert A

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

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

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

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