ML20073R465
| ML20073R465 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/04/1991 |
| From: | Anthony Mendiola Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073R467 | List: |
| References | |
| NUDOCS 9106070277 | |
| Download: ML20073R465 (4) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION j
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WASHINGTON. D.C. 2WA
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l ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 89 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Tne application for amendment by Alabama Power Company (the licensee),datedMay 17, 1991, 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 u
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 anendment; and paragraph 2.C.(2) of f acility Operating License No. NPF-2 is hereby amended to read as follows:
l 9106070277 910604 PDR ADOCK 05000348 P
-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
89, are hereby incorporated into the license. Alabama Power Company 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 Orignal signed by:
Anthony J. Mendiola, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 4, 1991 DFC
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.,7-1 DATE :6 /Sc/91
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- f/ Y/9 OFFICIAL RECORD COPY
e ATTACHMENT TO LICENSE AMENDMENT NO.
89 FACILITY OPERATING LICENSE NO. NPF-2 a
DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised arer are indicated by marginal lines.
Remove Pages Insert Pages 3/4 3-30 3/4 3-30 i
i I
o a
e TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES S
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.
Pressurizer Pressure-Lov Safety Injection (ECCS)
$ 27.0'*'/12.0
a.
b.
Reactor Trip (from SI)
< 2.0 c.
Feedvater Isolation
< 32.0
d.
Containment Isolation-Phase "A"
< 17.0
e.
Containment Purge Isolation
< 5.0 f.
Auxiliary Feedvater Pumps IlotApplicable g.
Service Vater System 5 77.0/87.0'I' 4
Differential Pressure Between Steam Lines-High a.
-Safety Injection (ECCS) i 12.0/22.0
b.-
Reactor Trip (from SI)
< 2.0 c.
Feedvater Isolation
< 32.0
d.
Containment Isolation-Phase "A"
$ 17.0/27.0
e.
Containment Purge Isolation Not Applicable f.
Auxiliary Feedvater Pumps Not Applicable g.
Service Vater System f 77.0'*'/87.0
5.
Steam Flov in Two Steam Lines-High Coincident vith T,y --Low-Lov a.
Steam Line Isolation f 11.0 l
6.-
Steam Line Pressure-Lov a.
Safety Injection (ECCS)-
f 12.0/22.0
b.-
Reactor Trip (from SI)
_ 2.0 c.
Feedvater Isolation
_ 32.0
d.
Containment Isolation-Phase "A"
$ 17.0/27.0
e.
. Containment Purge Isolation Not Applicable f.
Auxiliary Feedvater Pumps Not Applicable g.
Service Vater System
< 77.0/87.0
h.
Steam Line Isolation-
,7.0 F/RLEY - UNIT 1 3/4 3-30 AMEf;DMENT NO.
75, 89
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