ML17353A698
| ML17353A698 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/13/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17353A700 | List: |
| References | |
| NUDOCS 9605170511 | |
| Download: ML17353A698 (8) | |
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UNITED STATES NUCLEAR REGULATORY'COMMlSSlON WASHINGTON, D.C. 2055&0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE
'mendment No. 184 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 March 5,
- 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.
9605i705li 960513 PDR ADQCX O5OOO25O 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.B 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.
- 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 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:
May 13, f996
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT P ANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 178 License No.
DPR-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated March 5,
- 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.
2.
Accordingly, the l.icense 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)
Tec ical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 178, 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:
May i3, igg6 Frederick J.
Hebdon, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
EN MENT NO.
TTACHMENT TO LICENSE AMENDMENT FACILITY OPERATING LICENSE NO.
DPR-31 MENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NOS: 50-250 AND 50-251 Revise Appendix A as follows:
Remove a es 3/4 4-9 3/4 5-7 Insert a es 3/4 4-9 3/4 5-7.
REACTOR COO ANT SYST M
'3 4.4.3 PR SSURIZER IMITING COND ION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with a water volume: of less than or equal to 92X of indicated level, and at least two groups of pressurizer heaters each having a capacity of at least 125 kW and capable of being supplied by emergency power.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With only one group of pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the follow-ing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor Trip System breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.4.3. 1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified by energizing the heaters and measuring circuit current, at least once per 92 days.
TURKEY POINT UNITS 3
& 4 3/4 4-9 AMENDMENT NOS.184 AND 178
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS d.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and 2)
At least once daily of the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.
e.
At 2) least once per 18 months by:
Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 525 psig the interlocks cause the valves to automatically close and prevent the valves from being
- opened, and Verifying correct interlock action to ensure that the RWST is.
isolated from the RHR System during RHR System operation and to ensure that the RHR System cannot be pressurized from the Reactor Coolant System unless the above RWST Isolation Valves are closed.
3)
A visual inspection of the containment sump and verifying that the suction inlets are not restricted by debris and that the sump components (trash racks,
- screens, etc.)
show no evidence of structural distress or abnormal corrosion.
f.
At 2) least once per 18 months, during shutdown,'y:
Verifying that each automatic valve in the flow path actuates to its correct position on Safety Injection actuation test
- signal, and Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
a)
Safety Injection pump, and b)
RHR pump.
TURKEY POINT - UNITS 3
& 4 3/4 5-7 AMENDMENT NOS 184AND178
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