ML20129K376
| ML20129K376 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/20/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129K377 | List: |
| References | |
| NUDOCS 9611220139 | |
| Download: ML20129K376 (5) | |
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a =ezu UNITED STATES g
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20565 4001 o
.....g SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET N0. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 23, 1996, as supplemented by letters dated September 16, November 6,11 and 14, 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; j
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 tre 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 51 of the Comission'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:
9611220139 961120 PDR ADOCK 05000364 e
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(2)
Technical Soecifications l
The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No.117, are hereby incorporated in the l
license.
Southern Nuclear shall operate the facility in l
accordance with the Technical Specifications.
l 3.
This license anendment is effective as of its date of issuance and shall l
be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION He bert N. Berkow, Director Project Directorate II-2 i
Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications i
Date of Issuance: November 20, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT N0.117 l
TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 3/4 4-12a 3/4 4-12a l
3/4 4-13 3/4 4-13 l
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 3 6.
Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L*n criteria.
For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging.
For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be. removed from service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied.
Refer to 4.4.6.4.a.16 for the repair limit applicable to these intersections.
For a tube with an imperfection or flaw in the tubesheet below the lower joint of an installed elevated laser welded sleeve, no repair or plugging is required provided the installed sleeve meets all sleeved tube inspection requirements.
7.
Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.6.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side)-completely around the U-bend to the top support of the cold leg.
For a tube with a tube sheet sleeve installed, the point of entry is the bottom of the tube sheet sleeve below the lower sleeve joint.
For a tube that has been repaired by
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sleeving, the tube inspection should include the sleeved portion of the tube.
9.
Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, or, for elevated sleeves'", Southern Nuclear letters dated August 23, 1996, November 6, 1996, and November 11, 1996, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.
L* Criteria is applicable to Cycle 11 only.
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- The elevated tube sheet sleeve is authorized for installation l
only during the Unit 2 Eleventh Refueling outage.
FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO. 117
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 15.
Tube Expansion is that portion of a tube which has been increased in diameter by a rolling process such that no crevice exists between the outside diameter of the tube and the hole in the tubesheet.
Tube expansion also refers to that portion of a sleeve which has been increased in diameter by a rolling process such that no crevice exists l
between the outside diameter of the sleeve and the parent steam generator tube, i
l 16.
Tube Support Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service j
that is experiencing predominately axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair limit is based on maintaining steam generator tube serviceability as described below:
-a.
Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds cf the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit [2.0 volts), will be allowed to remain in
- service, b.
Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tu$, support plate with a bobbin voltage greater than the lower voltage repair limit
[2.0 volts), will be repaired or plugged except as noted in 4.4.6.4.a.16.c below.
c.
Steam generator tubes, with indications of potential degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit (2.0 volts] but less than or equal to the upper voltage repair limit *, may remain in service if a rotating probe inspection does not detect degradation.
Steam generator tubes, with indications of outside diameter stress corrosion i
cracking degradation with a bobbin voltage greater than the upper voltage repair limit *, will be plugged or repaired.
The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supplemented.
FARLEY-UNIT 2 3/4 4-13 AMENDMENT NO.117 l
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