ML17353A850
| ML17353A850 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/13/1996 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17353A852 | List: |
| References | |
| NUDOCS 9608150190 | |
| Download: ML17353A850 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 ORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No.
DPR-31 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated July 26,
- 1995, and additional information provided by letters dated March 13,
- 1996, May 3,
- 1996, and May 9,
- 1996, 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 facility will operate in conformity with the application, the provisions of the Act, and the rules 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 will not 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.
9608i50i90 9608i3 PDR ADOCK 05000250 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-31 is hereby amended to read as follows:
(8)
Technical S ecifications and Environmental Protection Plan 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 8 is hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
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.
H don, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1996
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.i84 License No.
DPR-41 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated July 26,
- 1995, and additional information provided by letters dated March 13,
- 1996, May 3,
- 1996, and May 9,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'.s rules and regulations'et forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules 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 will not 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-41 is hereby amended to read as follows:
(B)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, 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 facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August i3, ig96 Frederick J.
He don, Director Project Directorate II-3 Division of Reactor-Projects
- I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT M
DMENT NO. i 90 FACILITY OPERATING LICENSE NO.
DPR-31 MENDMENT NO."84 FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
Remove a
e Insert a
e
4
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ADMINISTRATIVE CONTROLS
~
PEAKING FACTOR LIMIT REPORT 6.g. 1.6 The W(Z) function(s) for Base-Load Operation corresponding to a +2N band about the target flux difference and/or a +3X band about the target flux difference, the Load-Follow function Fz(Z) and the augmented surveillance turnon power fraction, Pz, shall be provided to the U.S. Nuclear Regulatory Commission, whenever P~ is (1.0.
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 P~)
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 otherwise approved by the Commission.
The analytical methods 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.
CORE OPERATING LIMITS REPORT 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:
l.
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 -'Q(Z) for Specification 3/4.2.2.
4.
All Rods Out position for Specification 3. 1.3.2.
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 FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.
2.
WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT," September 1974.
The analytical methods used to determine 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.
2.
WCAP-9561-P-A, ADD. 3, Rev.
1, "BART A-1: A Computer Code for the'Best Estimate Analysis of Reflood Transients - Special Report:
Thimble Modeling W ECCS Evaluation Model."
3.
WCAP-10054-P-A, (proprietary),
"Westinghouse Small Break ECCS Evaluation Model Using the NOTRlJMP Code," August 1985.
~ TURKEY POINT UNITS 3 EE 4 6-20 AMENDMENT NOS. 190 AND i84
ADHINI STRATIV CON ROLS
(
4
~
CORE OPERATING LI ITS REPORT (Continued) 4.
WCAP-10054-P, Addendum 2, Revision 1 (proprietary)
"Addendum to the Westinghouse Small Break LOCA ECCS Evaluation Mode) Using the NOTRUHP Code: Safety Injection in the Broken Loop and Improved Condensation Model," October 1995.8 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, "Westinqhouse 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 Facility Operating License DPR-41, Florida Power
& Light Company Turkey Point Units 3 and 4, Docket Nos.
50-250 and 50-251.
The AFD, 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, 0 This reference is only to be used subsequent to NRC approval.
TURKEY POINT UNITS 3
& 4 6-21 AMENDMENT NOS. 190 AND184