ML20115J924
| ML20115J924 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/19/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20115J926 | List: |
| References | |
| NUDOCS 9607250155 | |
| Download: ML20115J924 (8) | |
Text
i
-,,- cy4 UNITED STATES yo j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001
\\...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY l
l DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. NPF-2 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated June 24, 1996, 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 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 Commission's regulations; D.
The issuance of this license 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, i
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:
9607250155 960719 PDR ADOCK 05000348 P
- (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B,.as revised through Amendment No. 120, 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.
FOR THE NUCLEAR REGULATORY COMMISSION t
rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 19,1996 i
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l ATTACHMENT TO LICENSE AMENDMENT N0.120 l
i TO FACILITY OPERATING LICENSE NO. NPF-2 1
DOCKET NO. 50-348 L
l Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indfi.ated by marginal lines.
i Remove Pace Insert Paae l
3/4 3-14 3/4 3-14 l
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TABLE 4.3-1 (continued $,
TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than 2 percent.
(3)
Compare incore to excore axial flux difference every 31 EFPD.
l Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4)
Manual ESF functional input check every 18 months. For the j
fourteenth operating cycle only, this test is not required until the next Mode 2 entry from Mode 3.
(5)
Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6)
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
- Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(8)
Logic only, if not performed in previous 92 days.
(9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and l
indicates no turbine trip prior to P-9.
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(10)
If not performed in the previous 31 days.
f (11)
Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.
Verify reactor trip breaker and reactor trip bypass breaker open (12) upon actuation of each Main Control Board handswitch.
(13)
Local manual shunt trip prior to placing breaker in service.
Local manual undervoltage trip prior to placing breaker in service.
(14) - Undervoltage trip via Reactor Protection System.
(15) - Local manual shunt trip.
t i
FARLEY-UNIT 1 3/4 3-14 AMENDMENT NO. 120
r A ltf C 24 UNITED GTATES 3j j
NUCLEAR REGULATORY COMMIESION o,
WASHINGTON, D.C. 2066Hm01 k.....,d j
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY l
DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 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 June 24, 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 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-8 is hereby amended to recd as follows:
l
(2)
Technical Soecifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.112, are.hereby incorporated in the license.
Southern Nuclear shall operate the facility in l
accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-l H rbert N. Berkow, Director l
Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: July 19, 1996 i
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 112 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 i
Replace the following page of the Appendix A Technical Specifice; ions with the enclosed page. The revised areas are indicated by marginal lines.
l Remove Paae Insert Paae 3/4 3-14.
3/4 3-14 G
M L
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o TABLE 4.3-1 (Continued) l TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
i (1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than 2 percent.
(3)
Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4).
Manual ESF functional input check every 18 months. For the eleventh operating cycle only, this test is not. required until the nexr. Mode 2 entry from Mode 3.
I (5)
Each train or logic channel shall be. tested at least every 62 l
days on a STAGGERED TEST BASIS.
l (6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(8)
Logic only, if not performed in previous 92 days.
l (9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.
(los -
If not performed in the previous 31 days.
(11)
Independently verify OPERABILITY of the undervoltage and shunt l
trip circuitry for the Manual Reactor Trip Function.
l f
(12)
Verify reactor trip breaker and reactor trip bypass breaker open upon actuation of each Main Control Board handswitch.
(13)
Local manual shunt trip prior to placing breaker in service.
Local manual undervoltage trip prior to placing breaker in service.
j.
(14)
Undervoltage trip via Reactor Protection System.
l (15)
Local manual shunt trip.
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FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 112
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