ML20084L981
| ML20084L981 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/22/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084L982 | List: |
| References | |
| NUDOCS 9506070369 | |
| Download: ML20084L981 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20566 0001 g,.....,/
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET N0. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No. NPF-2 s
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated March 6, 1995, 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 license 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 2.C.(2) of Facility Operating License No.
NPF-2 is hereby amended to read as follows:
9506070369 950522 PDR ADOCK 05000348 P
I i
. (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 115, are hereby incorporated in the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION H bert N. Berkow, Director s
oject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1995
ATTACHMENT TO LICENSE AMENO:1ENT NO. 115 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove _Paggi Insert Paaes IV IV 3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46 3/4 3-47 s
3/4 3-48 B 3/4 3-3 8 3/4 3-3
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...............................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR........................
3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR...............
. 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO.
....... 3/4 2-11 3/4.2.5 DNB PARAMETERS
.......... 3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION................ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......
..................... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring
......... 3/4 3-38 Movable Incore Detectors........................... 3/4 3-42 Getsmic "cnitoring Inctrumentetien(Deleted)......... 3/4 3-43 l
l "ctccrclogical Inctrumentetien(Deleted).............
3/4 3-46 l
Remote Shutdown Instrumentation..
3/4 3-49 Ghlerine Detection Syctc c(Deleted)........
.... 3/4 3-52 High Energy Line Break Sensors....
................ 3/4 3-53 Accident Monitoring Instrumentation................ 3/4 3-56 F4rc Detection Inctrumentation (Deleted)........... 3/4 3-59 Radicactive Liquid Effluent "cnitoring(Deleted)
.. 3/4 3-61 Waste Gas Monitoring....
.. 3/4 3-66 3/4.3.4 TURBINE OVERSPEED PROTECTION...
........ 3/4 3-72 FARLEY-UNIT 1 IV AMENDMENT NO.'1,05,00,111, 115
RISTRUMENTATION SEISMIC INSTRUMENTATION This specification deleted.
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I FARLEY-UNIT 1 3/4 3-43 AMENDMENT NO. u, 115 l
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l FARLEY-UNIT 1 3/4 3-44 AMENDMEffr No. G4, 115
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l FARLEY-UNIT 1 3/4 3-45 AMENDMENT NO. G4,8G, 115 1
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h If7STRUMEf7TATION METEOROLOGICAL INSTRUMEf7TATION This specification deleted.
Pages 3/4 3-47 and 3/4-48 deleted.
k FARLEY-UNIT 1 3/4 3-46 AMENDMENT NO. M, 115 i
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INSTRUMENTATION
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BASES i
3/4.3.3.3' SEISMIC INSTRUMENTATION This specification deleted.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION This specification deleted.
s 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
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3/4.3.3.7 HIGH ENERGY LINE BREAK ISOLATION SENSORS The high energy line break isolation sensors are designed to mitigate the consequences of the discharge of steam and/or water to the affected room and other lines and systems contained therein.
In addition, the sensors will initiate signals that will alert the operator : bring the plant to a shutdown condition.
FARLEY-UNIT 1 B 3/4 3-3 AMENDMENT NO. 2 f,111, 115 i
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p3 7E2m
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D.C. 20555-0001
'+9.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO. 50-364 M SEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated March 6, 1995, 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 license 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 i
51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical i
Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:
. (2)
Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 107, are hereby incorporated in the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director l
s Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1995 l
i l
l
ATTACHMENT TO LICENSE AMENDMENT N0,107 l
TO FACILITY OPERATING LICENSE N0. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
q
. Remove Paaes Insert Paaes IV IV 3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46 3/4 3-47 3/4 3-48 B 3/4 3-3 8 3/4 3-3 L
l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AX I AL FLUX D I FFERENCE............................... 3 / 4 2 - 1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.......................
.3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR........
... 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO.
.................. 3/4 2-11 3/4.2.5 DNB PARAMETERS................
..... 3/4 2-14 s
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................
3/4 3-1 j
3/4 3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..............
............... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION l
Radiation Monitoring....
.... 3/4 3-38 Movable Incore Detectors.............
.............. 3/4 3-42 Scicmic onitering Inctrumentation(Deleted).......... 3/4 3-43 l
"ctccr 1cgical Inctrumcatesten(Deleted)............. 3/4 3-46 l
Remote Shutdown Instrumentation...............
.. 3/4 3-49 1
Chlerinc Octcetier Syctc=c(Deleted)................ 3/4 3-52 High Energy Line Break Sensors......................
3/4 3-53 l
Accident Monitoring Instrumentation................ 3/4 3-56
.irc Octcction Inctru=cntation (Deleted)............
3/4 3-59 Radicacti/c Liquid "ffluent "cnitoring (Deleted)....
3/4 3-61 Waste Gas Monitoring
................... 3/4 3-66 3/4.3.4 TURBINE OVERSPEED PROTECTION........................
3/4 3-72 FARLEY-UNIT 2 IV AMENDMENT NO.SS,91,102, 107
INSTRUMENTATION f
SEISMIC INSTRUMENTATION This specification deleted.
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s FARLEY-UNIT 2 3/4 3 43 AMENDMENT NO.
107
b This page intentionally left blank.
l FARLEY-UNIT 2 3/4 3-44 AMENDMENT No.
107
I This page intentionally left blank.
FARLEY-UNIT 2 3/4 3-45 AMENDMENT NO.74, 107 l
l
INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION This specification deleted.
Pages 3/4 3-47 and 3/4 3-48 deleted.
4 FARLEY-UNIT 2 3/4 3-46 AMENDMENT No.
107
INSTRUMENTATION BASES 3/4.3.3.3 SEISMIC IM3TRUMENTATION This specification deleted.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION This specification deleted, s
3/4.3.3.5 REMOTE SHUTDOWN INSTP,
'ATION The OPERABILITY of the.
Atdown instrumentation ensures that sufficient capability is availaute to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
3/4.3.3.7 HIGH ENERGY LINE BREAK ISOLATION SENSORS The high energy line break isolation sensors are designed to mitigate the consequences of the discharge of steam and/or water to the affected room and other lines and systems contained therein.
In addition, the sensors will initiate signals that will alert the operator to bring the plant to a shutdown condition.
FARLEY-UNIT 2 B 3/4 3-3 AMENDMENT NO. Ma, 107 i
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