ML17354A933

Amends 196 & 190 to Licenses DPR-31 & DPR-41,respectively, Consisting of Changes to TSs in Response to Application & Suppl

ML17354A933
Person / Time
Site:	Turkey Point
Issue date:	05/12/1998
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML17354A934	List: ML17354A933 ML17354A935
References
NUDOCS 9805270140
Download: ML17354A933 (12)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 Amendment No. 196 License No. DPR-31 The Nuclear Regulatory Commission (the Commission) has found that:

The application for amendment by Florida Power and Light Company (the licensee) dated January 9, 1998, and supplemented April20, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-31 is hereby amended to read as follows:

(B)

The Technical Specifications contained in Appendix A, as revised through Amendment No. 19're hereby incorporated in the license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license.

The licensee shall operate the facilityin accordance with the Technical Specifications and the Environmental Protection Plan.-

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon, Direct Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation I

Attachment:

Changes to the Technical Specifications Date of Issuance:

Nay 12, 1998

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 G

C Amendment No. 190 License No. DPRQ1 The Nuclear Regulatory Commission (the Commission) has found that:

The application for amendment by Florida Power and Light Company (the licensee) dated January 9, 1998, and supplemented April20, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the r'ules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's

.regulations; D.

The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-41 is hereby amended to read as follows:

(B)

The Technical Specifications contained in Appendix A, as revised through Amendment No. 190, are hereby incorporated in the license.

The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license.

The licensee shall operate the facilityin accordance with the Technical Specifications and the Environmental Protection Plan.

'his license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J ebdon, Directo Project

'ctorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 12, 1998

196 p 190 0

C S

D Revise Appendix A as follows:

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5-4 6-22 a es 5-4 6-22

5.3.1 The core shall contain 152 fuel assemblies with each fuel assembly containing ~

fuel rods clad with Zircaloy-4 or ZIRLO", except that replacement of fuel rods by filler rods consisting of stainless

steel, or by vacant rod positions.

may be made in fuel assemblies if justified by cycle-specific reload analysis using NRC-approved methodology.-

The reactor core contains approximately 71 metric tons of uranium in the form of natural or slightly enriched uranium dioxide pellets.

Each fuel rod shall have a nominal active fuel length of M inches.

Should more than 30-individual rods in the-

core, or 10 fuel rods in any fuel assembly.

be replaced per refueling, a Special Report discussing the rod replacements shall be submitted to the Commission within 30 days after cycle startup.

5.3.2 The core shall contain 5 full-length control rod assemblies.

The full-length control rod assemblies shall contain a nominal 142 inches of absorber material.

The absorber material shall be silver, indium, and cadmium.

All control rods shall be clad with stainless steel tubing.

R T 5.4. 1 The Reactor Coolant System is designed and shall be maintained:

a.

In accordance with the Code requirements specified in Section 4.1 of the FSAR, with allowance for normal,degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of~ psig + 1R, and c.

For a temperature of 650'F.

except for the pressurizer which is 680'F.

5.4.2 The nominal water and steam volume of the Reactor Coolant System is g3Q cubic feet at a nominal Tavg of 574.2'F.

5.5.I The meteorological towers shall be located as shown on Figure 5.1-1.

TURKEY POINT - UNITS 3 & 4 5-4 AMENDMENT NOS H6 AND 19O

~3.

WCAP-10054-P, Addendum 2, Revision 1 (proprietary),

"Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP 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.**

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 (9) to Frank R. Orr (USNRC),

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

7.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"

S.

L. Davidson and T. L. Ryan, April 1995:

The analytical methods used to determine 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.

"Westinghouse 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 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:

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 Faci lity 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),

F<H, 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-cycl.e 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 Comnission.

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 stated in the Specifications within Sections 3.0. 4.0, or 5.0.

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

• "As evaluated in NRC Safety Evaluation dated December 20, 1997.

TURKEY POINT - UNITS 3 & 4 6-22 AMENDMENT NOS 196 AND 190

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