ML17354A751
| ML17354A751 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/20/1997 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17354A752 | List: |
| References | |
| NUDOCS 9801120204 | |
| Download: ML17354A751 (8) | |
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UN)TED STATES NUCLEAR REGULATORY COMMISSlON wAsHINeToN, D.c. Qosss-ooo~
Amendment No. 195 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 February 24,
- 1997, as supplemented by letters dated April 24 and December 4.
1997, 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 comon defense and security or to the health and safety of'he 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.
980i'f20204 97%220 PDR ADOCK 05000250 P
PDR 2.
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. 195, 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 COHHISSION
.)
Frederick J.
Heb on. 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:
December 20, 1997
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UNITED STATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D.C. 205QHS01 AIIIendment No. 189 l.icense No.
DPR-41 1.
The Nuclear Regulatory Commission (the Ce>>IIII'issioII) has Found that:
A.
The application f'r amerIdmeIIL by <lvr ida PoweI'fld I.l(/hL'IApany (the licensee) dated February 24,;l997, as ~upplemeI:ted by letters dated April 24 and December 4, l997, comnlies with the standards and requirements of the Atomic Fnergy Act of 1954.
>s aIoerided (the Act) and the Commission's ru'les and regulations set forth in 10 CFR Chapter I:
B.
The facility will operate in conformity wii.h the appl'ication, the provisions of the Act. and the rules and regulations of the Commission:
C.
There is reasonable assuraIIce (I).hat the aI;tivit:Ies authorized by this amendment can be conducted without endangering the health and safety of the public.
and (ii) i;hat 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.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.
1S9
. 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 Fr ederi ck J.
Hebdon
. 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:
December 20, l997
195 189 Revise Appendix A as follows:
6-21 6-22
C
A A
F 6.9.1.6 The W(Z) function(s) for Base-Load Operation corresponding to a +2K 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, Pz. shall be provided to the U.S. Nuclear Regulatory Cmmission, 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 Pz) 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 Cmmission.
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.
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 - FO(2) for Specification 3/4.2.2.
4.
All Rods Out position for Specification 3.1.3.2.
5.
Nuclear 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 Fq SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.
MCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES - TOPICAL REPORT." September 1974.
The analytical methods used to determine Fp(Z),
F>H and the K(Z) curve shall be those previously reviewed and approved by the NRC in:
1.
MCAP-9220-P-A, Rev. 1.
Mestinghouse ECCS Evaluation Model - 1981 Version,"
February 1982.
2.
MCAP-10054-P-A. (proprietary).
"Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August 1985.
TURKEY POINT - UNITS 3 & 4 6-21 AMENDMENT NOR 195AND 189
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.*
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 (8). "Acceptance for Referencing of the Topical Report WCAP-12945(P)
'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis.'" June 28, 1996.~
Letter dated June 13,
- 1996, from N. J. Liparulo (g) 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 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:
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), 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-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 Cmmission.
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 TURKEY POINT - UNITS 3 & 4 6-22 AMENDMENT NOS195 AND189