ML20206G334
| ML20206G334 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/30/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G338 | List: |
| References | |
| TAC-62811, TAC-62812, NUDOCS 8704140516 | |
| Download: ML20206G334 (10) | |
Text
.
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'o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION o
W ASHINGTON. D. C. 20555
.y
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ALABAMA POWER COMPANY e
i I
f DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.69 License No. NPF-?
1.
The Nuclear Reaulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated September 2,1986, as supplemented February 9, 25, and 27, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Acti and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 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 CFP Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operatino License No. NPF-? is hereby amended to read as follows:
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. (?) Technical Specifications The Technical Specifications contained in Appendices A and R, as revised through Amendment No. 69. 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 and shall be effective until the startup following the eighth refueling outage.
FOR THE NUCLEAR REGULATORY COPISSION Lester. Rubenstein, Director PWR Pro.iect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Farch 30,1987
\\
ATTACHMENT TO LICENSE AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 u
I Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paces insert Pages 3/4 7-20 3/4 7 70 3/4 7-?Oa I
e i
I 4
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PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or the failure of the system on which they are install would have no adverse effect on any safety-related system.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
Witn one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supportec system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS eMSSESSES S
4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.S.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but witnin 10 months of POWER OPERATION and shall include all snubbers within the scope of Specification 3.7.9.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. of Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *#
0 16 montns + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days T 25%
5,6,7 62 days T 2b%
8 or more 31 days _T 25%
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- Ine inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
- This is a one-time Technical Specification change until startup from the eighth refueling outage. Table 4.7-3 should be utilized during this interval to determine the subsequent visual inspection period.
FARLEY - UNIT 1 3/4 7-20 AMENDMENT NO. 55. 69
TABLE 4.7-3 Snubber Visual Inspection Schedule 4
Current
- Visual Number of Inoperable Next Visual Inspection Period
- Snubbers Inspection Period de 18 Months + 25%
0,1, 2 18 Months + 25%
3 12MonksT25%
4 6 Months T 25%
5,6' 4 Months T 25%
4 7
2 Months T 25%
8 or more 1 Month E25%
12 Months + 25%
0, 1 18 Months + 25%
2, 3 12 Months T 251 4
6 Months T 25%
5 4 Months T 25%
6, 7 2 Months T 25%
7
_ 25%
8 or more 1 Month 6 Months + 25%
0 12 Months + 25%
1 6 Months T 25%
2 4 Months T 25%
3, 4 2 Months 25%
T
_ 25%
5 or more 1 Month 4 Pbnths + 25%
0 6 Months + 25%
1 4 Months T 25%
2 2 Months T 25%
3 or more 1 Month 125%
2 Puntns + 25%
0 4 Months + 25:
1 2 Months ~ 2 5*.
~
2 or more 1 Month 325%
l 1 Penth + 25%
0 2 Months + 25%
1 or more 1 Month j25%
~
- Tne provisions of Specificat
- r. 4.0.2 are not applicable.
- Earlier visual inspections than required may be utilized.
If this option is chosen, the criteria for determining the next visual inspection period shall be the criteria associated with the earlier visual inspection period selected.
FARLEY - UNIT 1 3/4 7-20a AMENDt'.ENT NO. 69
[GKECy 'o UNITED STATES 8
I,'n NUCLEAR REGULATORY COMMISSION 3
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c wAsmNGTON, D. C. 20555
%,.... + gh ALARAMA POWED COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated September 2,1986, as supplemented February 9, 25, and 27, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Actl and the Commission'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 (111 that such activities will be conducted in 'ompliance with the Commission's regulations; c
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 read as follows:
.?.
(2) Technical Specifications The Technical Specifications contained in Appendices l
A and B as revised through Amendment No. 61, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective os of its date of issuance and shall be effective until the startup following the fifth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION Lester S.\\Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Chances to the Technical l
Specifications Date of Issuance: March 30, 1987 1
\\
(
ATTACHMENT TO LICENSE AMFNDMENT NO. 61 TO FACILITY OPERATING LICENSE NO. NPC-8 DOCKET NO. 50-364 I
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages insert Pages 3/4 7-70 3/4 7-70 3/4 7-20a i
4 t
i
PLANT SYSTEttS 3;).7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their f ailure or the f ailure of the system on which they are installed would have no adverse ef f ect on any safety-related system.
{I APPLICABILITY: M3 DES 1, 2, 3 and 4.
(M3 DES 5 and 6 for snubbers located on systems required UPERABLE in those MJDES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statenent for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by perfomance of the f ollowing augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed af ter four montns but witnin 10 months of POWER OPERATION and shall include all snubbers within the scope of Specification 3.7.9.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25 % from the date of the first inspection.
Utnerwise, subsequent visual inspections shall be perforened in accordance with the following senedule:
No. of Inoperable Snubbers Subseqsent Visual I
per Inspection Period Inspection Period *a O
18 montns + 25%
1 12 months 7 25%
2 6 months T 25%
3, 4 124 days T 25%
~ 25%
5, 6, 7 62 days 1
8 or more 31 days 1 25%
The snubbers may be categorized into tw: groups:
Those accessible and those inaccessible during reactor opere. ion.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- Tne provisions of Specification 4.0.2 are not applicable.
- inis is a one time Technical Specification change until startup from the fifth refueling outage. Table 4.7-3 should be utilized during this interval to determine the subsequent visual inspection period.
FARLEY - UNIT 2 3/4 7-20 AMENDMENT NO. y,61
TABLE 4.7-3 Snubber Visual Inspection Schedule Current Visual Number of Inoperable Next Visual Inspection Period
- Snubbers Inspection Period a 18 Months + 25%
0,1, 2 18 Months + 25%
3 12 Montfs 7 25%
~
4 6 Months 7 25%
5,6 4 Months ~ 25%
7 2 Months 7 25%
8 or more 1 Month ~ 25%
12 Months + 25%
0, 1 18 Months + 25%
2, 3 12 Months 7 25%
~
4 6 Months 7 25%
5 4 Months 7 25%
6, 7 2 Months T 25%
8 or more 1 Month 1 25%
6 tenths + 25%
0 12 Months + 25%
1 6 Months 7 2b%
~
2 4 Months 7 251 3, 4 2 Months 7 25%
7_ 2b%
5 or more 1 Month 4 Pbnths + 2bt 0
6 Months + 25%
1 4 Months ~ 25%
~
2 2 Montns 7 25%
7_ 25%
3 or more 1 Month 2 Months + 25k 0
4 Months + 25%
1 2 Months ~ 25s
~
2 or more 1 Month ~ 25%
1 Month + 25%
0 2 Months + 25%
1 or more 1 Month ~ 25%
~
- Tne provisions of Specification 4.0.2 are not applicable.
- Earlier visual inspections than required may be utilized.
If this option is chosen, the criteria for determining the next visual inspection period shall be the criteria associated with the earlier visual inspection period selected.
FARLEY - UNIT 2 3/4 7-20a AMEN 0 MINT NO. 61 l
l