ML17342A121
| ML17342A121 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/27/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17342A122 | List: |
| References | |
| NUDOCS 8507110546 | |
| Download: ML17342A121 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No.
DPR-31 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated February 15,
- 1985, as supplemented on April 17 and May 8, 1985, 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.
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:
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Technical S ecifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 115, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days of issuance.
FO THE NUCLE R
LATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
.June 27, 19Q5 ga, Chic Operating Reactors Branch ¹1 Division of Licensing
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No.
DPR-41 The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated February 15, 1985, as supplemented on April 17 and May 8, 1985, 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the coomon 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 Comission'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)
Technical S ecifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 109, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately and shall be implemented within 60 days of issuance.
FO THE NUCLEA REGULATORY COMMISSION e
a'r a, Operating Reactors Division of Licens e
B anch ¹I
Attachment:
Changes to the Technical
'pecifications Date of Issuance:
June 27, 1985
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
115 FACILITY OPERATING LICENSE NO.
DPR-31 AMENDMENT NO.
109 FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NO. 50-250 AND 50-251 Revise Appendix A as follows:
Remove Pa es 3.1-2a B3.1-3 Insert Pa es 3.1-2a B3. 1-3
MODERATOR TEMPERATURE COEFFICIENT 3.1.2.1 The moderator temperature coefficient (MTC) shall be:
a) b)
Less positive than or equal to 5.0 x 10-5 hk/k/oF for all rods withdrawn, beginning of the cycle life (BOL), hot zero THERMAL POWER (HZP) conditions; and Less positive than or equal to 5.0 x 10-5 Sc/k/oF from HZP to 7096 RATED THERMALPOWER condition; and c)
Less positive than or equal to 5.0 x 10-5 hk/k/oF from 7096 RATED THERMALPOWER decreasing linearly to less positive than or equal to 0 hk/k/oF at 10096 RATED THERMALPOWER condition; and d)
Less negative than -3.5 x 10< hk/k/oF for the all rods withdrawn, end of cycle life (EOL), RATED THERMALPOWER condition.
APPLICABILITY: Specification 3.1.2.la, b, and c - MODES 1 and 2+ only++.
Specification 3.1.2.1d - MODES 1, 2, and 3 only++.
ACTION:
a)
With the MTC more positive than the limits of Specifications 3.1.2.1a, b, or c above, operation in MODES 1 and 2 may proceed provided:
1)
Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive or equal to limits described in 3.1.2.1a, b, and c above within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> or be in HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion limits of specification 3.2.1, 2)
The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and 3)
A Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.3, within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the MTC to within its limitfor the all rods withdrawn condition.
b)
With the MTC more negative than the limit of Specification 3.1.2.ld above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
+ With Keff greater than or"'qual to l.
++ The above limits may be suspended during the performance of LOW POWER PHYSICS TESTS.
The reactor vessel materials have been tested to determine their initial RTNDT.
Adjusted reference temperatures, based upon the fluence and copper content of the material in question, are then determined.
The heatup and cooldown limit curves include the shift in RTNDT at the end of the service period shown on the heatup and cooldown curves.
The actual shift in NDTT of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTM E185-73, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.
Since the neutron spectra at the irradiation samples has a definite relationship to the spectra at the vessel inside radius, the measured transition shift for a sample can be related with confidence to the adjacent section of the reactor vessel.
The heatup and cooldown curves must be recalculated when the b RTNDT determined from the surveillance capsule is different from the calculated hRTNDT for the equivalent capsule radiation exposure.
The pressure-temperature limit lines shown for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in T.S. 0.20 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.
The limitations imposed on pressurizer heatup and cooldown and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.
B3.1.2.1 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
The most negative MTC, value to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.
These corrections involved subtracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperture at RATED THERMAL POWER conditions.
B3.1-3 Amendment Nos. 115 and 109