ML20215D190
| ML20215D190 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/05/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20215D193 | List: |
| References | |
| DPR-51-A-106 NUDOCS 8612160249 | |
| Download: ML20215D190 (13) | |
Text
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~4 UNITED STATES J
l NUCLEAR REGULATORY COMMISSION f
- ,E WASHINGTON, D. C. 20555
\\...../
ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated April 1, 1986, as supplemented August 22, October 14 and October 23, 1986, complies with the standards and reauirements 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; 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 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 requirenents 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. OPR-51 is hereby amended to read as follows:
8612160249 861205 DR ADOCK 05000313 p
PDR n_.
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Technical Specifications The Technical. Specifications contained in Appendices A and B, as revised through Amendment No.106, 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.
R THE NUCLEAR REGU ATORY C0PMISSION 2
ldt '
J 'h F. Stolz, Director P R Project Directorat #6 ivision of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 5,1986
(
ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE NO. OPR-51 DOCKET NO. 50-313-Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 110j 110j 110jl 110k 110k 1101 1101 110m 110m 110ml 110n 110n 1100 1100 11001 11001 11002 11002 l
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4.18 STEAM GENERATOR TUBING SURVEILLANCE Applicability Applies to the surveillance of tubing of each steam generator.
Objective To ensure integrity of the steam generator tubing through a defined inservice surveillance program, and to minimize exposure of personnel to radiation during performance of the surveillance program.
Specification 4.18.1 Baseline Inspection The first steam generator tubing inspection performed accor' ding to Specifications 4.18.2 and 4.18.3.a shall be considered as constituting the baseline condition for subsequent inspections.
4.18.2 Examination Methods Inservice inspection of steam generator tubing shall include a.
non-destructive examination by eddy current testing or oth,er equivalent techniques.
The inspection equipment shall provide a sensitivity that will detect defects with a penetration of 20 percent or more of the minimum allowable as manufactured tube wall thickness except for a sleaved tube at the lower sleeve end.
b.
For examination of the sleeved steam generator tubing at the lower sleeve end, the indications will be compared to those obtained during the baseline sleeved tube inspection.
Significant deviations between these indications will be considered sufficient evidence to warrant designation as a degraded tube.
Direct quantification of the 40 percent through-wall plugging limit is available with eddy-current testing.
4.18.3 Selection and Testing The steam generator sample size is specified in Table 4.18.1 The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.18.2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.18.4 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.18.5.
The tubes selected for each inservice inspection shall include at least 3%
of the total number of tubes in both steam generators; the tubes selected for these inspections shall be selected on a random basis except:
Amendment No. 24, AI, f(,106 110j l
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r a.
-The first sample inspection during each inservice inspection (subsequent to the_ baseline inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (>20%), except tubes in which the wall penetration has been spanned by a sleeve, and 2.
At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems, except where specific groups are inspected per Specification 4.18.3.a.3.
Amendment No. 24, AI, gg.106 110jl
A-tube inspection (pursuant to Specification 4.18.5.a.9) shall be l
performed on each selected tube.
If any selected tube does not permit the passage.of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
3.
Tubes in the following groups may be excluded from the first random sample if all tubes in a group in both steam generators are inspected.
The inspection may be concentrated'on those portions of the tubes where imperfections were previously found.
No credit will be taken for these tubes in meeting minimum sample size requirements.. Where only a portion of the tube is inspected, the remainder of the tube will be subjected to the random inspection.
(1) Group A-1:
Tubes within one, two or three rows of the open inspection lane.
(2) Group A-2:
Unplugged tubes with sleeves installed.
(3) Group A-3:
Tubes in the wedge-shaped group on either side of the lane region (Group A-1) as defined by Figure 4.18.1.
b.
The second and third sample. inspections during each inservice inspection as required by Table 4.18.2 may be less than a full tube inspection by concentrating the inspect. ion on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
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 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.
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Amendment No. 24, #I, Q7,106 110k
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NOTES:
(1)
In all inspections, previously degraded tubes whose degradations have not been spanned by a sleeve must 1
exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
(2)
Where special inspections are performed pursuant to 4.18.3.a.3, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not be included in determining the Inspection Results Category for the general steam. generator. inspection.
4.18.4 Inspection Intervals performed at the following frequencies:The above required inserv The baseline inspection shall be performed during the first a.
refueling shutdown.
Subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 24 calendar months after the previous inspection.
If the results of service under all volatile treatment (AVT) conditions the C-1 category or 'if two consecutive inspections demonstrate that previously observ.ed degradation has not continued and no-additional. degradat-ion has occ'urred,:the' inspection interval for that ~g~r'o'up may be extended to a maximum of 40 months.
~
b.
If the results of the inservice inspection of a steam generator performed in accordance with Table 4.18.2 at 40-month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.
The increase in inspection _ frequency shall apply until a subsequent inspection meets',the conditions specified in 4.18.4.a and the interval can be extended to 40 months.
Additional unscheduled inservice inspections shall be performed c.
on each steam generator in accordance with the first sample inspection specified in Table 4.18.2 during the shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary leakage in excess of the limits of Specification 3.10 (inservice inspection not required if leaks originate from tube-to-tubesheet welds),
2.
A seismic occurrence greater than the Operating Basis Earthquake,
^A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3.
Amendment No. 24, AI, 86,106 1101
~.
A 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or 4
4.
A main steam line or feedwater line break.
4.18.5 Acceptance Criteria a.
. As used in this specification:
1.
Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2.
Imperfection means an exception to the dim *ensions, finish or l
contour of a tube from that required by fabrication drawings or specifications.
Eddy current testing ind.ications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3.
Degradation means service-induced cracking, wastage, wear l
or general corrosion occurringon either the inside or outside of a tube.
4.
Degraded Tube means a tube containing imperfectipns 2 20% of the nominal wall thickness caused by degradation, except where all degradation has been spanned by the installation of a sleeve.
5.
% Degradation means the percentage of the tube wall j
thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging limit except where the imperfection has been spanned by the installation of a sleeve.
A tube containing a defect in its pressure boundary is defective.
7.
Plugging Limit means the imperfection depth at or beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next inspection; it is equal to 40% of the nomi,nal tube wall thickness.
~
8.
Unserviceable describes the condition of a tube if it leaks.
l 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 Specification 4.18.4.c.
9.
Tube Inspection means an inspection of the steam generator l
tube from the point of entry completely to the point of exit.
Amendment No. 24, #I, pp,106 110m
b.
' The steam generator. shall be determined operate af ter completing the corresponding actions-(plug or sleeve all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.18.2 j
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i-2 Amendment No. 24, #1, 46, 106 110ml l
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4.18.6 Reports Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC.
This report, to be submitted within 45 days of inspection completion, shall include:
a.
Number and extent of tubes inspected; b.
Location and percent of wall-thickness penetration for each indication of an imperfection; and c.
Identification of tubes plugged and tubes sleeved.
Bases The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the' RCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so { hat corrective measures can be taken.
Amendment No. 24, #I, 4,106 110n i
TABLE 4.18-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Preservice Inspection No No. of Steam Generators per Unit.
Two First Inservice Inspection Two Second & Subsequent Inservice Inspection Onel Table Notation:
4 The inservice inspection may be limited to one steam generator on alternating schedule encompassing 3N% of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous inspections indicate that all steam generators are performing in a like. manner.
Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators.
Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
Amendment No. 24, $$, 106 1100
g
_ TABLE 4.18-2 k.
STEAM GENERATOR TUBE. INSPECTION 2,3 s
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IST SAMPLE INSPECTION ll 2ND SAMPLE INSPECTION ll 3RD SAMPLE INSPECTION l
2 l Sample Size l Result l Action Required ll Result l Action Required ll Result l Action Required l
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my lA minimum of l C-1 l None ll N/A N/A ll N/A l'
N/A l
C 15 Tubes per l l
ll ll l
lS.G.1 l C-2 l Plug or sleeve ll C-1 l
None ll N/A I
N/A l
g l
l l defective tubes ll l
ll C-1 1 None l
l l
l and inspect ll C-2
[ Plug or sleeve ll C-2 Plug or sleeve l
l l
l additional 25 ll l defective tubes and ll
[ defective tubes l
i l
l l tubes in this ll l insp'ect additional 45 ll C-3 l Perform action for l l
l 1 S.G.
ll l tubes in this SG ll l C-3 result of I
l l
l ll C-3 l Perform action for ll l first sample l
I l
l ll l C-3 result of ll l
l l.
I 1
ll l first sample ll N/A l
N/A l
l l C-3 l Inspect all tubes ll Other l ll l
l o
1 l
l ip this S. G.
ll S.G. isl None ll N/A l
N/A l
~
l l
l p' lug or sleeve ll C-1 ll l
1 l
l l defective tubes ll Other Perform action for ll l
l l
l l and inspect 25 ll S.G. islC-2 results'of ll N/A l
N/A l
l l
l tubes in other ll C-2 I second sample ll l
l l
l l S.G.
ll Other l Inspect all tubes ll l
l l
l l
ll S.G. isl in each S.G. and ll N/A l
N/A l
l l
l ll C-3 l plug or sleeve ll l
l l
l l
ll l defective tubes.
ll l
l l
l l
ll l Request NRC approval ll l
l l
l l
ll l of remedial action.
ll l
l 85=3"% Where N is the number of steam generators in the unit, and n'is the number of steam NOTES:
generators inspected during an inspection.
2For tubes inspected pursuant to 4.18.3.a.3:
No action is required for C-1 results.
For C-2 results in one or both steam generators plug or sleeve defective tubes.
For C-3 results in one or both steam generators, plug or sleeve defective tubes and request NRC approval of remedial action.
3No more than ten thousand (10,000) sleeves may be installed in both ANO-1 steam generators combined.
1 l
FIGURE 4.18.1 Upper Tube Sheet View of. Wedge Shaped Group (Group A-3) per
- Speci fication 4.18.3. a. 3 i.e, i.
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Description Tube Count Group A-1:
Lane region tubes 382 l
as defined in 4.18.3.a.3.(1)
Group A-3: Wedge shaped group 4880 j.
depicted by darkened region of
.figure i
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Amendment No. M,106 11002 I
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