ML17341A914
| ML17341A914 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/18/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17341A915 | List: |
| References | |
| NUDOCS 8203030024 | |
| Download: ML17341A914 (9) | |
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UNITEDSTATES 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. 77 License No.
DPR-31 1.
The Nuclear Regulatory Commission (the CoIImission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated January 1, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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'uthorized 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.
."i~~PDR ADOCK.0500'0050..;;
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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)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 77
, 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 its issuance.
FO THE NUC EAR REGULATORY COMMISSION even A.
- arga, C i f Operating Reactors nch 41 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 18, 1982
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO.
50-251'URKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
71 License No.
DPR-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
The application for amendment by Florida Power and Light Company (the licensee) dated January 1, 1982, 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; The facility will'operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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 par agraph 3.B of Faci lity Operating License No.
DPR-41 is hereby amended to read as follows:
(B)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71
, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION teven ar a
C'i f g
~
Operating Reactors nch 81 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 18, 1982
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO.
DPR-31 Ah1ENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO.
DPR-41 e
DOCKET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
Remove Pa es 3.10-2 83.1 0-1 Insert Pa es 3.10-2 83.10-1
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5.
At least ONE residual heat removal pump shall be in operation, unless Tavg is less than 160F.
6.
klhen the reactor vessel head is removed and fuel is in he vessel, the minimum boron concentration of 1950 ppm or higher, sufficient to maintain the reactor subcritical by 1056k/<in the cold condi-tion with all rods inserted shall be maintained in the reactor coolant system and the concentration shall be verified daily.
7.
Direct communication between the control room and the refueling cavity manipulator crane shall be available during refueling operation.
8.
The spent fuel cask shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
9.
Fuel which has been discharged from a reactor will not be moved outside the containment in fewer than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown If any one of the specified limiting conditions for refuel-ing is not met, refueling shall cease until specified limits are met, and there shall be no operations which may increase reactivity.
3.10-2 Amendment Nos.
77
~ 71
B5.10 BASES FOR LIiiIITINGCONDITIONS FOR OPERATION, REFUELING Detailed instructions, safety precautions and the design of the fuel handling equipment, incorporating built-in inter-locks and safety features, provide assurance that no inci-dent could occur during the refueling operations that would result in a hazard to public health and safety.
When-(1) ever changes are not being made in core geometry one flux monitor is sufficient.
This permits maintenance of the instrumentation.
Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.
The residual heat pump is used to maintain a uniform boron concentration.
A boron concentration of 1950 ppm was sufficient to maintain the reactor subcritical by at least 10~~5,k/k in the cold condition with all rods inserted, and also maintained the core subcritical with no control rods inserted, for the first core design The required boron concentration (2) may increase depending on the subsequent core design.
Tne control room operator will be able to inform the manipu-lator operator of any impending unsafe condition detected from the control board indicators during fuel movement.
The cask crane interlocks prevent cask handling above spent fuel.
An excess weight interlock is provided on the spent fuel bridge crane hoist to prevent movement of more than one fuel assembly at a time.
The spent fuel transfer mechanism can accommodate only one fuel assembly at a time.
References (1)
FSAR - Section 9.5 (2)
FSAR Table 5.2.1-1 B3. 10-1 Amendment Nos.
77 8
71