ML17349A343
| ML17349A343 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/20/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17349A346 | List: |
| References | |
| NUDOCS 9208240168 | |
| Download: ML17349A343 (13) | |
Text
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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. 152 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 April 21,
- 1992, as supplemented May 19, June 2 and July 29,
- 1992, 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.
9208240168
'720820 PDR ADOCK 05000250 P
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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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 152, 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.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berk
, Director Project Directorate II-2 Division of Reactor. Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1992
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Ub1n'ED $TATEs 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.
147 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 April 21,
- 1992, as supplemented May 19, June 2 and July 29,
- 1992, 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'mendment 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 Oper ating License No.
DPR-41 is hereby amended to read as follows:
(B)
Technical S ecifications and Environment rotect'o Pla The Technical Specifications contained in Appendix A, as revised through Amendment No. i47, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
August 20, 1992
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 152 FACILITY OPERATING LICENSE'O.
DPR-31 MENDMENT NO. 147 FACILITY OPERATING LICENS NO.
DPR-41 DOCKET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
Remove a es 3/4 3-19 3/4 3-20 3/4 3-28 3/4 3-29 3/4 3-33a Insert a es 3/4 3-19 3/4 3-20 3/4 3-28 3/4 3-29 3/4 3-33a
TABLE 3.3-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION.SYSTEM INSTRUMENTATION C)
I I
C Qo FUNCTIONAL UNIT TOTAL NO.
OF CHANNELS 6.
Auxi1 iary FeedwaterQO (Continued) b.
Stm.
Gen. Mater Level--
3/steam Low-Low generator CHANNELS TO TRIP 2/steam generator 1n any steam generator MINIMUM CHANNELS OPERABLE 2/steam generator APPLICABLE MODES 1, 2, 3
ACTION 15 c.
Safety Injection See Item 1.
above for all Safety Injection initiating functions and requirements.
d.
Bus Stripping 1/bus 1/bus 1/bus 1, 2, 3
23 e.
Trip of All Main Feed-water Pumps Breakers 1/breaker 7.
Loss of Power
.1/br eaker)
(1/breaker) 1, 2
~
~
operating
./operating pump pump 23 CD CD CA Ui lQ a.
4.16 kV Busses A and B
2/bus (Loss of Voltage) 2/bus 2/bus 1, 2, 3, 4 18 b.
480 V Load Centers 3A, 3B, 3C, 3D and 4A, 4B, 4C, 40 Degraded Voltage Coincident with:
Safety Injection 2 per load 2 on any 2 per load 1, 2, 3, 4 18 center load center center See Item l. above for all Safety Injection initiating functions and requirements c-
TABLE 3. 3-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 7.
.Loss of Power (Continued)
MINIMUM TOTAL NO.
CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE APPLICABLE MODES ACTION 8.
9.
C.
d.
e.
Containment Radio-activity-High Containment Isolation Manual Phase A or Manual Phase.B Control Room Air Intake Radiation Level c.
480 V Load Centers 3A, 3B, 3C, 3D and 4A, 4B, 4C 4D Degraded Voltage Engineered Safety Features Actuation System Interlocks a.
Pressurizer Pressure b.
T
- Low Control loom Yentilation Isolation a.
Automatic Actuation Logic and Actuation Relays b.
Safety Injection 2 per load center 2 on any load center 2 per load 1, 2, 3, 4 18 center 1, 2, 3
1, 2, 3
19 19 1, 2, 3, 4,6"" 16 1, 2, 3, 4,6"~ 16 1, 2, 3, 4 17 All 24 See Item 1.
above for all Safety Injection initiating functions and -requirements.
2 1
1
a7 pcmC TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM
~FUNCTIONAL UNIT gl.
Loss of Power (Continued) b.
480V Load Centers Degraded Voltage Load Center ALLOMANCE TA)
Z S
TRIP SETPOINT ALLOWABLE VALUE 3A 3B 3C 3D 4A 4B 4C 4D E
3
[
3 E
3 E
3
[
]
[
3 E
3
[
3 E 3[
3 E 3[
3
[ 3[
3
[ 3[
3E 3
3[
3
[ 3[
3 E 3[3 430Vt5V 438V+5V 434V+5V 434V~5V 435V+5V 434Vi5V 434V+5V 430V+5V (10 sec + 1 (10 sec + 1 (10 sec + 1 (10 sec
+ 1 (10 sec
+ 1 (10 sec
+ 1 (10 sec
+ 1 (10 sec
+ 1 sec delay)[
3 sec delay)[ ]
sec delay)[ ]
sec delay)[ ]
sec delay)[ ]
sec delay)[ ]
sec delay)[ ]
sec delay)[ ]
m m
Coincident with:
Safety Injection and see item 1 See Item l. above for all Safety Injection Trip Setpoints and Allowable Values.
Q lO Diesel Generator Breaker Open N.A.
N.A.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM CD FUNCTIONAL UNIT I
g7.
Loss of Power (Continued}
c c.
480V Load Centers c
Degraded Voltage Load Center ALLOMANCE (TA TRIP SETPOINT ALLOMABLE VALUES GATI m
CD CA Vl IO CD 3A 3B 3C 3D 48 4C 4D Coincident with:
Diesel Generator Breaker Open N.A.
[]f ]
[ ][ ]
[ ][
[]f ]
[]f ]
[ ][ ]
[ ][ ]
[ ][
N.A. N.A 424V+5V(60 sec delay}
427V+5V(60 sec delay) 437V+5V(60 sec delay) 435V+5V(60 sec delay) 430V+5V(60 sec delay) 436V+5V(60 sec delay) 434V+5V(60 sec delay) 434VX5V(60 sec delay)
N.A.
sec t30
[ ]
sec
+30
[ ]
sec +30
[ ]
sec
+30
[ ]
sec +30
[ ]
sec +30
[ ]
[ ]
sec
+30
[ ]
N.A.
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION C
C/1 CHANNEL CHANNEL CHANNEL FUNCTIONAL UNIT CHECK CALIBRATION 6.
Auxiliary Feedwater (Continued)
TRIP ANALOG ACTUATING NODES CHANNEL DEVICE FOR MHICH OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE TEST TEST LOGIC TEST IS RE UIRED c.
Safety Injection See Item l. above for all Safety Injection Surveillance Requirements.
d.
Bus Stripping N.A.
R N.A.
N.A.
123 e.
Trip of All Hain Feedwater Pump Breakers.
7.
Loss of Power a.
4.16 kV Busses A
and B (Loss of Voltage)
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
1, 2 1, 2, 3, 4 m
foal b.
480V Load Centers 3A,38,3C,3D and 4A,4B,4C,4D Degraded Voltage Coincident with:
Safety Injection c.
480V Load Centers 3A,3B,3C,3D and 4A,4B,4C,40 Degraded Voltage N.A.
H(1)
N.A.
I, 2, 3, 4
~
See Item l. above for all Safety Injection Surveillance Requirements.
S R
N.A.
H(1)
N.A.
1, 2, 3, 4