ML20212A222
| ML20212A222 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/17/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212A226 | List: |
| References | |
| NUDOCS 9710230212 | |
| Download: ML20212A222 (8) | |
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UNITEE) STATES O
3 NUCLEAR REGULATORY COMMISSION j
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SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO' 50 348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13G Ucense No. NPF 2 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 7,1997, 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; 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:
9710230212 971017 PDR ADOCK 05000348 P
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2-(2)
Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.130, are hereby incorporated in the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective es of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w
erbert N. Berkow, Director Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance:
October 17, 1997 i
9 ATTACHMENT TO LICENSE AMENDMENT NO.130 TO FACILITY OPERATING LICENSE NO. NPF 2 DOCKET NO. 50 3f3 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised area is indicated by marginallines.
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Page 3/4 615 Page 3/4 615
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coNTAtleert SYSTEMS JURVIILLANCE RE001MMDfrS (continued) 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDCMN or REFUELING HODES or,defueled l
at least once per 18 months by Verifying that on a Phase A containment isolation test signal, a.
each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE prior to startup af ter each COLD SHUTDOWN if not performed in the previous 3 months by verifying that when the measured leakage rate is added to the leakage rates for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60L,.
In addition, the leakage rate for the containment purge isolation valves shall be coapared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.
An engineering evaluation shall be performed to determine what corrective action, if any, is necessary.
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FARLEY-UNIT 1 3/4 6-15 AMENDMENT No.130 l
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SOUTHERN NUCLFAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO. 50 384 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 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 7,19g7, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Acu, and the Commission's rules and rsgulations 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.4 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 ir.dicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating L! cense No. NPF 8 is hereby amended to read as follows:
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y 2-(2)
Technleal Sneelfications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.123, 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 b '
t H rbert N. Berkow, Director Project Directorate 112 Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation s
Attachment:
Changes to the Technical Specifications Date of issuance:
October 17, 1997 a
ATTACHMENT TO LICENSE AMENDMENT NQJ21 TO FACILITY OPERATING LICENSE NO. NPF 8 DOCKET NO. 50 384 Replace the following page of the Appendix A Technical Specificaticns with tSc enclosed page. The revised area is indicated by marginal lines, Remove jaasa Page 3/4 615 Page 3/4 615 9
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4.6.3.2 Each isolation valve specifled in Table 3.6 1 shall be demonstrated CPERABLE during the COLD SWTDOWN or REFUELING MODES or defueled l
at least once per 18 months by:
Verifying that on a Phase A containment isolation test signal, a.
each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B contairunent isolation test signal, each Phase B isolation valve actuates _a its isolation position.
6.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to specification 4.0.5.
4.6.3.4
'the containment purge isolation valves shall be demonstrated CPERABLE prior to startup after each COLD SHUTDOWN if not performed in the previous 3 months by verifying that when the measured leakage rate is added to the leakage rates for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60L..
In addition, the leakage rate for the containment purge isolation valves shall be compared to the previously measured leakage rate (for the containment purge isolation valves) to detect excess valve degradation.
An engineering evaluation shall be performed to detemine what corrective action, if any, is necessary.
FARLEY-UNIT 2 3/4 6-15 AMENDMENT NO.123
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