ML20028G449
| ML20028G449 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/02/1983 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20028G432 | List: |
| References | |
| NUDOCS 8302090363 | |
| Download: ML20028G449 (5) | |
Text
1.
Technical Specification Change Request No.123 The Licensee requests that the attached changed pages replace the following pages of the existing Technical Specifications.
Appendix A T. S. 4.19 pages 4-80, 81, 82, 85 II.
Reasons for the Change Request At the present time, Technical-Specifications. require in-part successful completion of a periodic inservice inspection program of the steam generator tubes in order to confirm steam generator operability.
T.S. 4.19 further indicates that where the inservice inspection program identifies tube defects, the tube in question will be removed from service by plugging.
The proposed change recognizes that for certain types of steam generator tube defects, other methods of repair may exist or may be developed to remcve the defect from service.
The change provides the flexibility to permit other repair,
methods to be used with the review and approval of the NRC Staff.
i III.
Safety Analysis Justifying Change No new method of repair is proposed in this amendment. Any alternate repair methods proposed by the Licensee will require submission of a separate Safety Analysis for evaluation by the Staff.
Thus, this change does not involve an increase in the probability or consequences of accidents previously evaluated, does not introduce accidents c.her than those previously evaluated, and does not reduce any safety margin.
IV.
Amendment Classification (10 CFR 170.22)
This change request is administrative in nature and has no safety or environmental significance and is therefore considered a Class 11 license amendment.
A check in the amount of $1,200.00 will be forwarded under separate C o Ver.
V.
Implementation It is requested that the NRC act on this request by March 1, 1963.
8302090363 830202 PDR ADOCK 05000289 P
'2.
A seismic occurrence greater than the Operating Basis Earthquake.
3.
A loss of coolant accident requiring actuation of the engineering. safeguards,,or 4.
A major main steam line or feedwater line break.
4.19.4 Acceptance Criteria e
a.
As used in this Specification:
- 1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabricati~on_ drawing or specifications.
Eddy current testing indications below 20% of-_the nominal tube wall thickness, if detectable, may be considered as imper fec tions.
- 2. Degradation means 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 thickness af fected 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.
I-
- 6. Repair Limit means the imperfection depth at or beyond which the shall be removed f rom service 'j '
degraded tube or portion of a tube t
because it may become unserviceable prior to the next inspection,.
and is equal to 40% of the nominal tube wall thickness, unless higher limits are shown to be acceptable by analysis and approved by the NRC.
- 7. Unserviceble describes the condition of a tube if it leaks or contains a defect large enough to affect its structurel integrity in the event of an Operating Basis Earthquake, a loss of coolant accident, or a steam line or 'feedwater line break as specified ia 4.19.3.c, above.
- 8. Tube Inspection means an inspection of.the steam generator tube from the bottom of the upper tubesheet completely to the top of the lower tubesheet, except as permitted by 4.19.2.b.2, above.
4-80
b.
The steam generator shall be determined. 0PERABLE af ter completing the
. corresponding actions (repair of all tubes exceeding the repair limit and all tubes containing throughwall cracks by plugging or b,y any other-repair method shown to be acceptable by analysis, and approved by the NRC) required.by Table 4.19.2.
4.19.5 Reports Following the completion of each inservice inspection of steam generator a.
tubes, the number of tubes repaired in each steam' generator shall beI reported to the NRC within 15 days.
- b. The completed results of the steam generator tube inservice inspection shall be report ed to the NRC within 3 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 an imperfection.
3.
Identification of tubes repaired.
I
- c. Results of steam generator tube inspections. which fall into Category ! -3 C
and require prompt notification of the NRC shall be reported pursuant to Specification 6.9.2 prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent rec urrence.
Bases The Surveillance Requirements for inspection of the steam generator tubes insure that.the structural integrity of this portion of the RCS will be maintained.
4-81
w The program for. ineervice inspection of steam generator. tubes is bcsed 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. mcchanical damage or progressive degradation due to design, manufac turing errors, or inservice conditions.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any' tube degradation so that corrective measures can be taken.
The Unit is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these chemistry limits, localir.ed corrosion may likely result in stress corrosion cracking.
The extent of steam generator tube leakage due to cracking would be limited by the secondary coolant activity, Specification 3.1.6.3.
The extent of cracking during plant operation would be limited by the limitation of total steam generator tube leakge between the primary coolant system and the secondary coolant system (primary-t o-secondary leakage = 1 gpm).
Leakage in
. excess of this limit will require plant shutdown and an unscheduled in s p e c t ilon,
during which the leaking tubes will be located and repaired by removal of;the tube or degraded portion of the tube from service by plugging or a repair method shown to be acceptable by analysis, and approved by the NRC.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect would develop in service, it will be found during scheduled inservice steam generator tube examina tions.
Repair of the degraded tube or portion of tube will be required for degradation equal to or in excess of 40% of the tube nominal wall thickness, unless higher limits are shown to be acceptable by analysis and are reviewed and approved by the' NRC.
Repair will be accomplished by plugging or by a repair method shown to.be acceptable by analysis, and approved by the NRC.
Steam generator tube inspec--
tions of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube uall thickness.
I Where experience in similar plants with similar water chemistry, as documented by USNRC Bulletins / Circulars, indicate critical areas to be inspected, at least 50% of the tubes inspected should be from these critical areas.
First sample inspections sample size may be modified subject to NRC review and approval.
4-82
TAB?E /.19 2 51EAM GENEllATOft TUCE INSPECTION IST SAMPLE INSPECTION l
7ND SAMPt.E INSPECTION 3RD SAMPLE INSPECTION Sample Site flesult Action Required fle ult Action Ilc<luletti Result Action Requir-J A minimum ni C-1 None N/A N/A N/A, N/A S Tubes ner S. G.(l)
C-2 Repair defcctive C-1
' None -
N/A N/A tules and Inspect N
h pair ctive tubes and inspect C-2 hy,g,ir defective additional 2S C-2 tubes in this ndditionni 4S Periosm actiori Inr S.G.
tubesin this C-3 C-3 result of fitst semple S.c.
Perform action for.
C-3 C-3 result of first N/A N/A s.impic p
C,-3 Impcct all tuber in Other this S. G., repair dc
- S.C. is None
- N/A N/A m*
fective tubes end C-1 Irn;iett 25 tubes in Other
'"" '" I
IA I^
other S.G.
3*b-C-2 result el secomf frompt notification to Ni1C pursuant
- I to specification Other Imrret all tubes in 6.9.2.
3,g.
3, each S. G. and repair de:lective tubes.
C-1 Prom t notification
'N/A N/A to NRC pursuant to specificatinn
- 6. 9_. 2.
Notes:
(1) 3 334 Ypierg N is the number of stearn generetors In the unit. arut tiIn the number of steem generators intpected during an inspection n
(2) For tubes inspected pursuant to 4.19.2.a.4:
No action is required for C-1 results.
For C-2 results in one or both steam generntors repair defective tubes.
For C-3 results in one or both steam generators, repair defective tubes and provide prompt notification of NRC pursuant to specification 6.9.2.
.