ML20107J990
| ML20107J990 | |
| Person / Time | |
|---|---|
| Site: | Farley  (NPF-02-A-051, NPF-08-A-042, NPF-2-A-51, NPF-8-A-42) |
| Issue date: | 10/17/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20107J992 | List: |
| References | |
| TAC-55609, TAC-55610, NUDOCS 8411120429 | |
| Download: ML20107J990 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION
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ALABAMA POWER COMPANY DOCKET N0. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT N0. I AMENDMENT TO FA.CILITY OPERATING LICENSE Amendment No.51 License No. NPF-2 1.
_The Nuclear Regulatory Cornission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated August 17, 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 conformity with the application, as amended, the provisions of the Act, and the 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:
F411120429 841017 C
PDR ADOCK 05000348 P
(2) Technical Specifications
-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 51, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION LO
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Operating Reactors nch #1 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance: October 17, 1984 a
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ATTACHMENT TO LICENSE AMENDMENT N0. 51
- AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO.- 50-348 Revised Appendix A as follows:
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PLAMT SYSTEMS SURVEILLANCE REQUIREMENTS (Continu:d) 2.
Verifying thet each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.
3.
Verifying that the stop check valves 3350A, 3350B, and 3350C are in the open position with the breaker to the valve operators locked open.
b.
At least once per 18 months by:
Verifying that each automatic valve in the flow path actuates to its correct position on an auto pump start signal.
c.
At least once per 18 months during shutdown by:
1.
Verifying that each motor driven pump starts automatically upon receipt of each of the following test signals:
a) Safety injection, b)
Steam generator water level low-low in any steam generator, and c) Loss of Site Power (LOSP).
2.
Verifying that the steam turbine driven pump starts automatically upon receipt of each of the following test signals:
a) Undervoltage on 2 out of 3 reactor coolant pump buses, and b)
Steam generator water level low-low in two steam generators.
3.
Verifying that the turbine-driven auxiliary feedwater pump l
steam admission valves Q1N12V001A-A and Q1U12V001B-B will open when air is supplied from their respective air accumulators, d.
The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 following each COLD SHUTDOWH by performing a flow test to verify the nonnal flow path from the emergency condensate storage tank through each auxiliary pump to its associated steam generator. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
FARLEY-UNIT 1 3/47-5 AMENDMENT NO. 51
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UNITED STATES
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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated August 17, 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 conformity with the application, as amended, the provisions of the Act, and the 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 conducted in compliance with the Comission'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 E:
of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingl;, 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 read as follows:
L
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.-2_
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is efft.ctive as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/1 N.,
1 4
en ga, t
Operating Reactors Bqan b #1 Division of Licensing v
Attachment:
Changes to the Technical-Specifications Date of Issuance: October 17, 1984
ATTACHMENT TO LICENSE AMENDMENT N0. 42 AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:
Remove Page Insert Page 3/4 7-5 3/4 7-5 6
i 4
k-
['
l
{
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continu3d) t 2.
Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater systen is placed in automatic control or when above 101 RATED THERMAL POWER.
, ; 3.
Verifying that the stop check valves 3350A, 3350B, and 3350C are in the open position with the breaker to the valve operators locked open.
b.Qt least once per 18 months by:
Verifying that each automatic valve in the flow path actuates to its correct position on an auto pump start signal.
c.
At least once per 18 months during shutdown by:
1.
Verifying that each motor driven pump starts automatically upon receipt of each of the following test 31gnals:
a)
Safety injection, b)
Steam generator water level low-low in any steam generator, and c) Loss of Site Power (LOSP).
2.
Verifying that the steam turbine driven pump starts l
automatically upon receipt of each of the following test signal s:
a) Undervoltage on 2 out of 3 reactor coolant pump buses, and b)
Steam generator water level low-low in two steam generators.
- 3. _ Verifying that the turbine-driven auxiliary feedwater pump l
steam admission valves Q2N12V001A-A and Q2N12V001B-B will open when air is supplied from their respective air accunulators.
d.
The auxiliary feedwater system shall be demonstrated OPERABLE prior to entry into MODE 2 following each COLD SHUTDOWN by perfoming a flow test to verify the nomal flow path from the emergency condensate storage tank through each auxiliary pump to its associated steam generator. The provisions of Specificatiori 4.0.4 are not applicable for entry into MODE 3.
FARLEY-UNIT 2 3/47-5 AMENDMENT H0. 42 L
.