ML20235D491
| ML20235D491 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/21/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235D493 | List: |
| References | |
| TAC-65287, NUDOCS 8709250244 | |
| Download: ML20235D491 (10) | |
Text
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ALABAMA POWER COMPANY DISTRIBUTION See attached DOCKET NO. 50-364 list JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 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 May 4, 1987, 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 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-8 is hereby amended to read as follows:
8709250244 070921 PDR ADDCK 05000364 P
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Technical Specifications j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64
, are hereby incorporated in the license. The licensee i
shall operate the facility in accordance with the l
Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt of this amendment.
i FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director i
Project Directorate 11-1 i
Division of Reactor Projects I/II l
Attachment:
l Changes to the Technical Specifications Date of Issuance: September 21, 1987 l
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e ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 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 4-9 3/4 4-9 3/4 4-10 3/4 4-10 3/4 4-12 3/4 4-12 3/4 4-13 3/4 4-13 3/4 4-13a 3/4 4-15 3/4 4-15 B3/4 4-3a B3/4 4-3a F
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3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing Tavg above 200'F.
SURVEIL!d.;4E REQUIREMENTS 4.4.6.0,Each steam generator shall be demonstrated OPERABLE by performance of the following augmented 1.nservice inspection program and the requirements of Specification 4.0.5.
i 3
4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam generator f
shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4 The tubes selected for each inservice inspection shall include at least 3% of the 8
total number of tubes in all steam generators.
Selection of tubes to be inspected is not affected by the F* designation. When applying the exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous defects or imperfections in the j
area repaired by sleeving are not considered an area requiring reinspection.
1 The tubes selected for these inspections shall be selected on a random basis j
except:
Where experience in similar plants with similar water chemistry a.
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations greater than 20%.
- When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.6.4.a.9.
FARLEY-UNIT 2 3/4 4-9 AMENDMENT NO. M,64
SURVEILLANCE REQUIREMENTS (Continued) l 1
....-----...--w.............------==.-............
2.
Tubes in those areas where experience has. indicated potential problems.
'3. At least 3% of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for the inspection program, whichever is less. These inspections will
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include both the tube and the sleeve.
q 4.
A tube inspection (pursuant' to Specification 4.4.6.4.a.8) shall be
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performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and'an adjacent tube shall be selected and subjected to a tube inspection.
j The tubes selected as the second and third samples (if required by c.
T.able 4.4-2) during each inservice inspection may be subjected to a
, partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections include those portions of the tubes where imperfections were previously found.
'i The results of each sample inspection shall be classified into one of the following three categories:
Category inspection Results C-1 Less than 5% of the total tubes inspected are '
f degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than 10%) further wall penetrations to be 1ncluded in the above percentage calculations.
4.4.6.2.2 Steam Generator F* Tube Inspection - In addition to the minimum sample size as determined by Specification 4.4.6.2.1, all F* tubes will be inspected within the tubesheet region. The results of this inspection will not be a cause for additional inspections per Table 4.4-2.
FARLEY-UNIT 2 3/4 4-10 AMENDMENT NO. $$,64
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
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q 4.4.6.4 Acceptance Criteria q
a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions, finish or i
contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall thickness, if detectable, may~ be considered i
as imperfections.
j 2.
Degradation means a service-induced cracking, wastage, wear or.
general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Degraded Tube means a tube, including the sleeve if the tube has been repaired, that contains imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
S.
Defect means an imperfection of such severity tnot it exceeds the plugging or repair limit. A tube or sleeve containing a defect is i
defective.
i 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 to the area of the tubesheet region below the F* distance in F* tubes.
For a tube that has been sleeved, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in 4
the sleeve requires the tube to be removed from service by plugging.
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 cide) completely around the U-bend to the top support of the cold leg. For a tube that has been repaired by 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, 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.
FARLEY-UNIT 2 3/4 4-12 AMENDMENT NO. g, 64
f 4
REACTOR COULANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
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- 10. Preservice Inspection means an inspec each tube in each Steam generator performed by eddy curfent techniques prior to service to establish a baseline condition of This' inspection shall be performed after the field j
the tubing.
hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
1 11.
F* Distance is the distance of the expanded partion 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 1.79 inches and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower i
in elevation.
12.
F* Tube is a tube:
a) with degradation equal to or greater than 40% below the F*
distance, and b) which has no indication of imperfections 4
i greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains in service.
l
- 13. Tube Expansion is that portion of a tube which has been increased i
in diameter by a rolling process such that no crevice exists
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between the outside diameter of the tube and the hole in the
'l tubesheet.
b.
The steam generator shall be determined OPERABLE after-completing the corresponding actions (plug or repair of all tubes exceeding the plugging or repair limit) required by Table 4.4-2.
'O 4.4.6.5 Reports Following each inservice inspection of steam generator tubes, the a.
number of tubes plugged, repaired or designated F* in cach steam i
i generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort, l
b.
The complete results of the steam generator tube and sleeve inservice inspection shall be submitted' to the Commission in a'Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
1.
Number and extent of tubes and sleeves inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged or repaired.
FARLEY-UNIT 2 3/4 4-13 AMENDMENT ' NO. 46, 63," 6<
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0-REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
Results of steam generator tube' inspections which' fall:into Category c.
C-3 shall be considered a REPORTABLE EVENT and shall be reported
.Tn e.
pursuant to 10CFR50.73 prior to resumption of plant operation.
written report shall provide a' description of investigations conducted to determine the 'cause of-the tube degradation and corrective measures taken to prevent recurrence.
_o l
FARLEY-UNIT 2 3/4 4-13a AMENDMENT NO. 46,53,64
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- 3. The tube plugging limit continues to apply to the portion of the tube j
in the entire upper joint region and in the. lower roll expansion.
As noted above the sleeve plugging limit applies to these areas also.
- 4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper. 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.l.79 inches and is measured down from the top of the tubesheet or.the bottom of the-roll transition, whichever 1s lower in
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elevation.
Included in this distance is an allowance of 0.25 inch for eddy current elevation measurement uncertainty.
1 Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 20%
of the original. tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10CFR50.73 prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a.
requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necess ary.
-e FARLEY-UNIT 2 B3/4 4-3a AMENDMENT NO. 53, 64
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