ML20247M302
| ML20247M302 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20247M294 | List: |
| References | |
| NUDOCS 8909250178 | |
| Download: ML20247M302 (7) | |
Text
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LTST OF TABLES TABLE TITLE pAGE l
1.2 Frequency Notation 1-8 1
2.3-1 Reactor Protection System Trip Setting Limits 2-9 3.1.6.1 Pressure Isolation Check Valves Between the Primary 3-15a Cooiant System and LPIS l
3.5.1 Instruments Operating Conditions 3-29 3.5-1A Quadrant Tilt Limits 3-34a 3.5.2 Accident Monitoring Instruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d 3.21-1 Radioactive Liquid Effluent Monitoring Instrumentation 3-97 3.21-2 Radioactive Gaseous Process and Effluent 3-101 Monitoring Instrumentation 3.23-1 Radiological Environmental Monitoring Program 3-122 3.23-2 Reporting Levels for Radioactivity Concentration 3-126 in Environmental Samples 4.1-1 Instrument Surveillance Requirements 4-3 4.1-2 Minimum Equipment Test Frequency 4-8 4.1-3 Minimum Sampling Frequency 4-9 4.1-4 Post A::cident Monitoring Instrumentation 4-10a 1
4.21-1 Radioactive Liquid Effluent Monitoring 4-88 Instrumentation Surveillance Requirements 4.21-2 Radioactive Gaseous Effluent Monitoring 4-91 Instrumentation Surveillance Requirements 4.22-1 Radioactive Liquid Waste Sampling & Analysis Program 4-96 4.22-2 Radioactive Gaseous Waste Sampling & Analysis Program 4-102 1
4.23-1 Maximum Values for the Lower Limits of Detection (LLD) 4-118 i
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Amendment No. 59, 72, 100, 106, 118, 137, 142, 147 890925017s 890913 FDR ADOCK 03000289 P
4,19 OTSG TUBE INSERVfCE 2NSpECTION Applicability This Technical Specification applies to the inservice inspection of the OTSG tube portion of the reactor coolant pressure boundary.
Objective The objective of this inservice inspection program is to provide assurance of continued integrity of the tube portion of the Once Through Steam Generators, while at the same time minimizing radiation exposure to personnel in the performance of the inspection.
Specification Each steam generator shall be demonstrated OPERABLE by performance of the following inservice inspection program and the requirements of l
Specification 3.1.6.3.
4.19.1 Steam Generator Sample Selection and Inspection Methods a.
Both steam generators shall be determined OPERABLE during shutdown by selecting and inspecting the steam generators at the frequency specified in 4.19.3.
b.
Inservice inspection of steam generator tubing shall include nondestructive examination by eddy-current testing or other equive. lent techniques. The inspection equipment shall bn calibrated to provide a sensitivity that will detect defects with a penetration of 20 percent or mote of the minimum allowable as-manufactured tube wall thickness.
4.19.2 Steam Generator Tube Sample Selection and Inspection The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.19.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.19.4.
The tubes selected for each inservice inspection shall include a nominal 20% of the total number of inservice tubes in each steam generator such that 100% inspection of the inservice tubes in each steam generator, over five inspection (refueling) intervals, is achieved.
The tubes selected for each inservice inspection shall include a representative sample of tubes to include areas identified by relevant industry (OTSG) experience as likely to produce higher degraded or defective tube population I
densities.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjace.'t (or representative) tube shall be selected and subjected to a tube inspection.
l 4-77 Amendment No. 47 (12-22-78)
4.19.2.1
. The following additional tubes shall be inspected during each refueling interval inspection:
- 1. All non-plugged tubes that previously had detectable wall penetrations (>20% T.W.).
Tubes may be exempted (from the "each refuelirg" interval inspection requirements) in future examinations if no damage progression (>20% T.W. increase) over 3 successive inspections is recorded and an engineering evaluation is performed.
- 2. Tubes having wear indications at or near the tube support plates.
4.19.2.2 Based on the results of the refueling interval inspection, the sample size will be expanded / modified as follows:
- 1. If active degradation has been found in a generator, with the exception of 4.19.2.1.1 above, then additional tubes or portions of tubes, necessary to bouna the problem, will be inspected.
- 2. All tubes such that at least two unplugged defect-free tubes are found in all applicable directions from a tube containing a defect that is considered to be an isolated occurrence.
- 3. partial tube length inspection of the area of interest may be permitted where experience supports the isolated location of degradation.
4.19.3 Inspection Frequencies The required inservice inspections of cteam generator tubes shall be performed at the following frequencies:
a.
Inservice inspections should be performed every refueling interval, not more than 24 calendar months after the previous inspection.
4-78 Amendment No. 47 (12-22-78) g
=
b.
Additional, unscheduled inservice inspections of sample size sufficient to determine the extent of OTSG tube damage shall be performed on affected steam generator (s) dur5ng the shutdown subsequent to any of the following conditions:
- 1. Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds or previously plugged tubes) in excess of the limits of Specification 3.1.6.3.
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- 2. A seismic occurrence greater than the Operating Basis Earthquake.
- 3. A loss of coolant accident requiring actuation of the Engineered Safeguards, or
- 4. A major main steam line or feedwater line break.
4.19.4 Acceptance Criteria a.
As used in the Specification:
- 1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawing 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, I
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 thickness affected or removed by degradation.
- 5. Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
4-79 Amendment No. 47, 116, 149
- 6. Repair Limit means the extent of degradation at or beyond which the tube shall be repaired or removed from service because'it may become unserviceable prior 5.the next inspection.
This limit is equal to 40% of the nominal tube wall I
thickness.
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- 7. Unserviceable describes the condition of a tube 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 requiring i
1.
actuation of the Engineered Safeguards, or main steam line or feedwater line break.
- 8. Tube Inspection means an inspection of the steam j
. generator tube from the bottom of the upper tubesheet completely to the top of the lower tubesheet, except as permitted by 4.19.2, above.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (removal from service by plugging, or repair by kinetic expansion, sleeving, or other methods, of all tubes exceeding the repair limit and all tubes containing through wall cracks) required to repair defective tubes or remove them from servfD.
4.19.5 Reports a.
Following the completion of each inservice inspection of steam generator tubes, the numbu af tubes repaired or removed from service in each steam generator shall be reported to the NRC within 15 days.
b.
The complete results of the steam generator tube inservice inspection shall be reported to the NRC within 12 months following completion of the inspection. This report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of degradation.
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- 3. Identification of tubes repaired or removed from service.
- 4. Basis for determining that the extent of occurrence of new defective tubes has been satisfactorily bounded by additional sample inspection performed.
4-80 Amendment No. 47, 83, 91, 103, 116, 129, 149
Bases The Surveillance Requirements for inspections 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 Electric Power Research Institute (EPRI "PWR Steam Generator Inspection Guidelines, Rev. 2.").
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.
Inservice inspection of steam generator tubing also provities a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
All non plugged steam generator tubes will be inspected over 5 consecutive inspection intervals.
The Unit is expected to be operated in a manner such that the primary and secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the primary or secondary coolant chemistry is not maintainen within these chemistry limits, localized corresion may result.
The extent of tube degradation during plant operation would be limited by the limitation of total steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 1 gpm).
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and repaired or removed from service.
Wastage-type defects are unlikely with proper chemistry treatment of the primary or secondary coolant.
However, even if a defect would develop in service, it will be found during scheduled inservice steam generator tube examinations.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the criginal tube wall thickness.
Where damage mechanisms are determined to be relevant to TMI-1 based on experience in similar steam generators (OTSGs) in other plants, a representative sample of tubes in those suspect areas will be included in the inservice inspection sample. When active degradation is found, additional inspection (s) will occur to bound the problem.
If an isolated occurrence, at least two unplugged defect free tubes will be found in all applicable directions from the tube containing a defect.
If its a systematic occurrence, then sufficient tubes will be inspected to bound the problem. The tubes examined in the additional sample expansion should be examined tubesheet to tubesheet unless there is testing or experience to support the isolated occurrence of defects in the vertical plane.
Plugging or repair will be required for degradation equal to or in excess of 40% of the tube nominal wall thickness.
4-81 Anandment No. 47, 66., 116, 149 (Pages 4-82 to 4-85 deleted)
.g.
(8) Repaired Steam Generators In order to confirm the leak-tight integrity of the Paactor Coolant System, including the steam generators, operation of the facility shall be in accordance with the following:
1.
GPU Nuclear Corporation shall confirm baseline primary-to-secondary leakage rate established during the steam generator hot test program.
If leakage exceeds the baseline leakage rate by more than 0.1 gpm, the facility shall be shut down and leak tested.
If any increased leakage above baseline is due to defects in the tube free span, the leaking tube (s) shall be removed from service. The baseline leakage shall be re-established, provided that the leakage limit of Technical Specification 3.1.6.3 is not exceeded.
(9) Long Range Planning Program The " Plan for the 1.ong Range Planning Program for the Three Mile Island duclear Station - Unit 1" (ths Plan) submitted by GPUN letter C311-88-2030 dated March 16, 1988 is approved.
a.
The Plan shall be followed by the Licensee from and after May 27, 1988.
b.
The Category A schedule shall not be changed without prior approval from the NRC.
Categories B and C schedules may be changed without prict approval by NRC.
This license is effective as of the date of issuance and shall expire at midnight, May 18, 2008.
FOR THE ATOMIC ENERGY COMMISSION Original Signed by A. Giambusso A. Giambusso, Deputy birector for Reactor Projects Directorate of Licensing
Attachment:
Appendix A Technical Specifications Date of Issuance: April 19, 1974
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