ML20134D438
| ML20134D438 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/11/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134D440 | List: |
| References | |
| NUDOCS 9610220244 | |
| Download: ML20134D438 (5) | |
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UNITED STATES ye 4
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001 o
- ...+g SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET N0. 50-364 i
JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACIllTY OPERATING LICENSE l
Amendment No.116 License No. NPF-8 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated April 22, 1996, as j
supplemented by letters dated May 3, July 15, August 7 and 30, and September 16, 1996, complies with the standards and i
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; j
C.
There is reasonable assurance (i) that the activities authorized 1
by this amendment can be conducted without endangering the health i
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 i
Part 51 of the Commission's regulations and all applicable i
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:
9610220244 961011 PDR ADOCK 05000364 P
l
. (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.116, 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 A
'L2^ ulo L
erhtN.Berkow,Direcflor Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: October 11, 1996
I ATTACHMENT TO LICENSE AMENDMENT NO.116 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET N0. 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 Paaes Insert Paaes 3/4 4-12b 3/4 4-12b B 3/4 4-3b B 3/4 4-3b I
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f REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 10.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial _ POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
11.
F* Distance is the distance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist pullout of the tube from the tubesheet. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the roll transition, whichever is lower in elevation. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.
12.
F* Tube is a tube:
I a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains inservice.
If the above criteria cannot be met, then the L* tube criteria may be applied or the tube must be plugged or repaired.
13.
L* Length. is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the J
tube sheet, which ever is lower, that has been determined to be 1.45 i
inches.
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14.
L* Tube..: a) is a tube with degradation equal or greater than 40%
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below the L' length and not degraded within the L* length; b) the eddy current indication of degradation below the L*' length must be determined to be the result of cracks with an orientation no greater than 15 degrees from axial; c) the L* criteria shall be limited t, a maximum of 600 tube ends per steam generator; d) tubes qualifying as F* tubes are not classified as L* tubes; el a minimum of 3.1 inches of the tube into the tubesheet from the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique or an inspection method shown to give equivalent or better information on the orientation and length of axial cracks; f) a minimum aggregate of 2.07 inches of sound roll expansion; g) a maximum crack length of.39 inches; h) a maximum of 5 distinct indications with a single band of tube degradation; and 1) that remains in service.
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- L* Criteria is applicable to Cycle 11 only.
FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.
116
I REACTOR COOLANT SYSTEM BASES 3.
The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.
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4.
The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
b.
Laser Welded 1.
Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.
2.
Indication of tube ce,radation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.
3.
At the weld joint, degradation must be evaluated in both the sleeve and tube.
4.
In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.
5.
The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.
F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.
L* is similar to F*; however, bands of axial degradation are allowed as long as sufficient non-degraded tubing is available to ensure structural and leakage integrity.
L* criterion is only applicable for Unit-2 Cycle 11.
Provided below is the Unit 2 Cycle 11 specific L* criterion:
FARLEY-UNIT 2-B 3/4 4-3b AMENDMENT NO. Il6