ML20117C364
| ML20117C364 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Turkey Point |
| Issue date: | 08/14/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114F973 | List: |
| References | |
| FOIA-84-661 NUDOCS 8505090399 | |
| Download: ML20117C364 (10) | |
Text
_
'*g UNITED STATES
'[T,.<ig NUCLEAR REGULATORY COMMISSION 7,
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W ASHINGTON, D. C. 20555
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FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-31 1.
The Nuciear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated August 6,1982, as modified on September 1, 1982, January 3,1983, April 25,1983, January 31, 1984 and April 23, 1984, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 comon 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-31 is hereby amended to read as follows:
g50g9841204 BELL 84-661 ppa
1
-2 (B) Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. '04, are hereby incorporated in the license.
The Itcensee 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.
F0Fl THE NUCL AR RGULATORY COMMISSION llvenA.
v(,,
rga, Chief Operating Reactors Bra
- 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 14, 1984 j
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s UNITED STATES
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NUCLEAR REGULATORY COMMISSION g,
WASWNGTON, D. C. 20555 m
I FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Awndment No. gg License No. DPW-41 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated August 6,1982, as modified on September 1, 1982, January 3,1983, April 25,1983, January 31, 1984 and April 23,1984, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 h
conducted in compliance with the Comission'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 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:
_2 (B) Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective.imediately and shall be implemented within 60 days of issuance.
FORTHENUCLEARREh qvenb \\-
rga, Chief Operating Reactors Bra 1
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 14, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-41 i
DOCKET NO. 50-250 AND 50-251 Revise Appendix A as follows:
I Remove Pages Insert Pages Table 3.5-2 Table 3.5-2 Table 3.5-2 (cont'd)
Table 3.5-4 Table 3.5-4 Sheets 1 and 2 Table 4.1-1 Sheet 3 Table 4.1-1 Sheet 3 f
L e
l
TABLE 3.5-2 ENGINEERED SAFETY FEATURES ACTUATION 1
2 3
MIN.
DEGREE OPERATOR ACTION MIN.
OF IF CONDITIONS OF OPERABLE REDUN-COLUMN 1 OR 2 NO.
FUNCTIONAL UNIT CHANNELS DANCY CANNOT BE MET 1.
SAFETY IN3ECTION 1.1 Manua!
1 0
Cold Shutdown 1.2 High Containment Pressure 2
1 Cold Shutdown 1.3 High Differential Pressure between any Steam Line and the Steam Line Header 2
1 Cold Shutdown 1.4 Pressurizer Low Pressure
- 2 1
Cold Shutdown i
1.5 High Steam Flow in 2/3 1/line 1
Cold Shutdown Steam Lines with Low in each Tavg or Low Steam of 2 Line Pressure lines 2.
CONTAINMENT SPRAY 2.1 High Containment Pressure 2 per 1/ set Cold Shutdown and High-High Containment set Pressure (coincident) 3.
AUXILIARY FEEDWATER 3.1 Low-Low Steam Generator 2
1 Hot Shutdown Level 3.2 Loss of Power a.
4.16kV Emergency Bus undervoltage (Loss of Voltage) 2 0
Cold Shutdown b.
480V Load Centers (2 instantaneous relays
.l, per load center)**
1***
O Cold Shutdown c.
480V Load Centers (2 inverse time relays per load center)**
1***
O Cold Shutdown 1
T18:S Amendments 104 and 98
-.~
TABLE 3.5-2 (Cont'd.)
ENGINEERED SAFETY FEATURES ACTUATION I
2 3
MIN.
DEGREE OPERATOR ACTION MIN.
OF IF CONDITIONS OF OPERABLE REDUN-COLUMN 1 OR 2 NO.
FUNCTIONAL UNIT CHANNEL 5 DANCY CANNOT BE MET 3.3 Safety injection
(-See 1 above-)
3.4 Trip of both Main 2
0 Cold Shutdown Feedwater Pump Breakers
- This signal may be manually bypassed, when the reactor is shutdown and pressure is below 2000 psig.
- These items do not apply on Unit 3 until after implementation of PC/M 79-116 and on Unit 4 until after implementation of PC/M 8044.
- Operation or start-up may continue with only one channel operable only if the inoperable channel is placed in the trip condition.
4 l
1 T18:.]
Amendments 104 ed 98
TABLE 3.5-4 (Sheet 1)
ENGINEERED SAFETY FEATURE SETPOINTS No.
FUNCTIONAL UNIT CHANNEL ACTION SET POINT 1.
High Containment Pressure Safety Injection
$6 psig Containment Spray
- Steam Line Isolation
- Containment Isolation
- 2.
High-High Containment See No. I 130 psig Pressure 3,
Pressurizer Safety Injection 21715 psig Low Pressure 4.
High Steam Line Safety injection
$150 psi Differential Pressure (2/3 between any header and any line) 5.
High Steam Line Flow Safety injection d/p for 3.34 x 106.
(2/3 lines)
Steam Line Isolation Ib/hr,770 psig, 100% RP d/p for 0.64 x 106 lb/hr,1005 psig,
(
0% RP d/p linear with Ist stg. press.,
0-100% RP Coincident with:
Low Steam Line Pressure, or 2600 psig Low Tavg 2531 F 6.
Low-Low Steam Generator Auxiliary Feedwater
> 15% narrow Level 7ange 1
7a.
Loss of Voltage (either Auxiliary Feedwater N.A.
4 KV bus) l High and High-High coincident T13:4
TABLE 3.5-4 (Sheet 2)
ENGINEERED SAFETY FEATURE SETPOINTS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETPOINT 7b.
Degraded Voltage "
Auxiliary Feedwater All with tolerance (480 Volt Load Center) of 1 volts.
5 Instantaneous Delay Load Center Setooint Setooint 3A**
436V (10 sec. delay)#
419V (60 see +30 sec. delayT 3B**
416V (10 sec. delay)#
426V (60 see +30 sec. delayT 3C**
417V (10 sec. delay)#
427V (60 see +30 sec. delayT 3D" 428V (10 sec. delay)#
436V (60 sec +30 sec. delayT 4A**
415V (10 sec. delay)#
427V (60 sec 130 sec. delay) 4B" 414V (10 sec. delay)#
424V (60 sec 130 sec. delay) 4C" 401V (10 sec. delay)#
413V (60 see +30 sec. delayT 4D'*
403V (10 sec. delay)#
412V (60 sec 130 sec. delay) 8.
Safety Injection Auxiliary Feedwater All SI setpoints 9.
Trip of both Main Auxiliary Feedwater N. A.
Feedwater Pump Breakers
- These items do not apply on Unit 3 until after implementation of PC/M 79-116 and on Unit 4 until after implementation of PC/M 80-44.
- Channel action is subject to condition being concurrent with Safety Injection signal.
l T18:5 Amendments 1G4 and 98
d
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,i TABLE 4.1-I SHEET 3 l
l Channel Description Check Calibrate Test Remarks 23.
Environmental Radiological Monitors N.A.
A(1)
M(1)
(1) Flow 24.
Logic Channels N.A.
N.A.
Mt 25.
Emer. Portable Survey instruments N.A.
A M
26.
Seismograph N.A.
N.A.
Q Make trace. Test battery (change semi-annually) 27.
Auxiliary Feedwater Flow Rate Mt R
N.A.
28.
RCS Subcooling Margin Monitor Mt R
N.A.
29.
PORY Position Indicator (Primary Detector)
Mt N.A.
R Check consists of monitoring 10.
PORV Block Valve Position Indicator Mt N.A.
R indicated position and verifying 31.
Safety Valve Position Indicator Mt R
N.A.
by observation of related
[
parameters.
32.
a.
Loss of Voltage (both 4kv bussess)
N.A.
N.A.
R For AFW actuation at power only b.
IJndervoltage (both 4KV busses and St R
Mt 480 volt Load Centers)"
- 33.
Trip of both Main Feedwater N.A.
N.A.
R For AFW actuation at power Pump Breakers only This item does not apply on linit 3 until af ter implementation of PC/M 79-116 and on Unit 4 until af ter implementation of PC/M 80 44.
l 39 AmendmenLs ini and 98 N