ML19296A941
| ML19296A941 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/15/1980 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19296A939 | List: |
| References | |
| TAC-41001, NUDOCS 8002190501 | |
| Download: ML19296A941 (7) | |
Text
TECHNICAL SPECIFICATION CHANGE REQUEST NO. 59 (APPENDIX A)
Replace pages 3/4 4-7, 3/4 4-8, 3/4 4-9, 3/4 4-10, and 83/4 4-3 with the attached revised pages 3/4 4-7, 3/4 4-8, 3/4 4-9, 3/4 4-10, 3/4 4-12a, and B3/4 4-3.
Proposed Change Add Specification 4.4.5.2.d as follows:
" Tubes in specified limited areas which are distinguished by unique operating conditions and/or physical con-struction may be excluded from random samples if all such tubes in the spe-cific area of a steam generator are insoected.
No credit will be taken for these tubes in meeting minimum sample size requirements."
Revise Specifications 4.4.5.3 b, 4.4.5.4.b, Bases 3/4.4.5, and add Table 4.4-6 to fully incorporate the change into the CR-3 Technical Specifications.
Reason for Proposed Change Operational experience has shown that tube defects can be the result of unique operating conditions and/or physical arrangements in certain limited areas of the steam generators (e.g., tubes adjacent to the open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled).
To include these tubes in the random sample of tubes to be in-spected could yield degraded or defective tubes that are not representative of the total population of tubes in the steam generator.
The proposed change will inspect all of these distinctive tubes, and will, therefore, detect all degraded or defective tubes in these areas.
Because of this total inspection, the tubes in these areas are not included in the representative sample for the steam generator, and will, therefore, not ar-tificially cause a shorter surveillance interval.
Safety Analysis of Proposed Change This Proposed Change does not reduce the margin of safety of the present Technical Specifications.
Without this Proposed Change, tubes in specific limited areas that have tube defects caused by unique operating conditions and/or physical arrangements will be included in the general tube popula-tion for selecting a sample.
This could cause an unnecessary increase in the number of tubes inspected because of defects in the sample.
This Proposed Change will not impact the present sampling requirements but will, instead, enhance them.
If these specific limited areas are complete-ly inspected, all defective or degraded tubes will be detected.
As this complete inspection of certain specified areas will be in addition to the present sampling, and it does not reduce the margin of safety provided by the requirements of Regulatory Guide 1.83, Rev.1, July 1975, no unreviewed safety question is involved.
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.
The first inservice inspection (subsequent to the preservice in-spection) of each steam generator shall include:
1.
All nonplugged tubes tnat previously had detectable wall penetrations (>20%), and 2.
Tubes in those areas..iiere experience has indicated poten-tial problems, c.
The second and third inservice inspections may be less than a full tube inspection by concentrating (selecting at least 50% of the tubes to be inspected) the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
d.
Tubes in specific limited areas which are distinguished by unique operating conditions and/or physical construction may be excluded from random samples if all such tubes in the specific area of a steam generator are inspected with the inspection result classi-fication and the corresponding action required as specified in Table 4.4-6.
No credit will be taken for these tubes in meeting minimum sample size requirements.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 57,of the total tubes inspected are de-graded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the to-tal 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 de-graded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must ex-hibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
CRYSTAL RIVER - UNIT 3 3/4 4-7
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Insoection Frequencies - The above-required inservice inspections of steam generator tubes shall be performed at the following frequencies:
a.
The first inservice inspection snall be performed after 6 Effec-tive Full Power Months, but within 24 calendar months of initial cri tical i ty.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under all volatile treatment (AVT) conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category, or if two consecutive in-spections demonstrate that previously ooserved degradation has not continued and no additional degradation has occurred, the in-spection interval may be extended to a maximum of once per 40 months.
b.
If the inservice inspection of a steam generator, conducted in accordance with Table 4.4-2 and/or Table 4.4-6 requires a third l
sample whose results fall in Category C-3, the inspection fre-quency shall be reduced to at least once per 20 months.
The re-duction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
c.
Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample in-spection specified in Table 4.4-2 and/or Table 4.4-6 during the
[
shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary tube leaks (not including leaks origin-ating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, 2.
A seismic occurrence greater than the Operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engi-neered safeguards, or 4.
A main steaa line or feedwater line break.
4.4.5.4 Acceptance Criteria a.
As used in this Specification:
1.
Imoerfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings CRYSTAL RIVER - UNIT 3 3/4 4-8
' REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service-induced cracking, wastage., wear, or general corrosion occurring on either inside or outside of a tube.
3.
Degraded Tube means a tube containing imperfections )20% of the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of the tube wall thick-ness affected or remove.d by degradation.
5.
Defect means an imperfection of such severity that it ex-ceeds the plugging limit. A tube containing a defect is de-fective. Any tube which does not permit the passage of the eday-current inspection probe shall be deemed a defective tube.
6.
Plugging Limit means the imperfection depth at or beyond whicn the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or coatains a defect large enough tc affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feeduater line break as specified in 4.4.5.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube fran tne point of entry completely to the point of exit.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2 (and Table 4.4-6, if the provisions of Specifica-tion 4.4.5.2.d are utilized).
4.4.5.5 Reports a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
CRYSTAL RIVER - UNIT 3 3/4 4-9
REACTOR COOLANT SYSTEM SURtEILLANCE REQUIREMENTS (Continued) b.
The complete results of the steam generator tube inservice in-spection shall be included in the Annual Operating Report for the period in which this inspection was completed.
This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
c.
Results of steam generator tube inspections which fall into Cate-gory C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determir.e cause of the tube degradation and corrective measures taken to prevent recurrence.
4.4.5.6 The steam generator shall be demonstrated OPERABLE by verifying steam generator level to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
CRYSTAL RIVER - UNIT 3 3/4 4-10
O Di TABLE 4.4-6 SPECIFIC LIMITED AREA IIISPECT10tl Mc E
IST SAMPLE If45PECT10ll UF A 2!10 SAMPLE lilSPECTI0li 0F A Il
" SPECIFIC LIMITED AREA"
" SPECIFIC LIMITED AREA" us I
Sample Size Result Action Required Result Action Required 100% of Area in both S.G.'s C-1 Ilone N/A fl/A C-2 Plug defective tubes fl/A ti/A ua2 C-3 Plug defective tubes II/A N/A p
SI 100% of Area in one S.G.
C-1 None N/A N/A C-2 Plug defective tubes and C-1 tione inspect 100% of corres-ponding area in other S.G.
.C-2 Plug defective tubes C-3 Plug defective tubes C-3 Plag defective tubes and C-1 lione inspect 100% of corres-ponding area in other S.G.
C-2 Plug defective tubes C-3 Plug defective tubes e
REACTOR COOLANT SYSTEM BASES imposed during normal operation and by postulated accidents.
Operati ng plants have demonstrated that primary-to-secondary leakage of 1 GPM can be detected by monitoring the secondary coolant.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Operational experience has shown that tube defects can be the result of unique operating conditions and/or physical arrangements in specific limited areas of tne steam generators (for example, tubes adjacent to the open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled). A full inspection of all of the tubes in such spe-cific limited areas will provide complete assurance that degraded or defec-tive tubes in these areas are detected.
Because no credit is taken for these distinctive tubes in the constitution of the first sample or its re-sults, the requirements for the first sample are unchanged.
This require-ment is essentially equivalent to and meets the intent of the requirements set forth in Regulatory Guide 1.83, " Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes", Rev.1, July 1975, and does not re-duce the margin of safety provided by those requirements.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in ser-vice, it will be found during scheduled inservice steam generator tube ex-aminations. Plugging will be required for all tubes with imperfections ex-ceeding the plugging limit of 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspec-tion fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant op-eration.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory exami-nations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
The steam generator water level limits are consistent with the initial conditions assumptions in the FSAR.
CRYSTAL RIVER - UNIT 3 B 3/4 4-3