ML20151R854
| ML20151R854 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/04/1986 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20151R847 | List: |
| References | |
| NUDOCS 8602060274 | |
| Download: ML20151R854 (6) | |
Text
.
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 a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by faorication drawing or specifications.
Eddy current testing indications below 20% of the nominal tube wall thickness, if detectable, nay be considered as i nperfections.
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 degra da tion.
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.
6.
Repair Limit means the extent of degradation at or beyond which the tube shall be repaired or removed from service because it nay become unserviceable prior to the next inspection.
This limit is equal to 40% of.the nominal tube wall thickness, except for the primary side tube freespan.,
For the prinary side tube freespan, the repair limit is either:
a.
50% of the nominal tube wall thickness and defect length of 0.55 inches or less; or 4-80 Amendment No. 47, 86 8602060274 e60204 PDR ADOCK 05000289 P
V b.
40% of the nominal tube wall thickness and defect length greater than 0.55. inches; or c.
40% of the nominal tube wall thickness in areas of reduced eddy current sensitivity (upper and lower tubesheet secondary faces and support plate entry and exit locations).
This primary side repair limit applies until Refueling Outage 6R, at which time the repair limit for the prinary tube freespan will be such a limit as has been approved by the NRC.
7.
Unserviceable de:.cribes 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, or a steam line or feedwater line break as specified in 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.
4-80a Amendment No. 47, 86
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 mintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical dange or progressive degradation due to design, anufacturing errors, or inservice conditions.
Inservice inspaction 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 enner such that the primry and secondary coolant will be mintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the primry or secondary coolant chemistry is not l
mintained within these chemistry limits, localized corrosion my l
likely result.
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 leakage between the primry coolant' system and the secondary coolant system (primry-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 and removed from service.
Wastage-type defects are unlikely with proper chemistry treatment of the primry 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 original tube wall thickness.
Plugging or repair will be required for degradation equal to or in excess of 40% of the tube nominal wall thickness, except for the primry tube freespan.
For the primry side tube freespan, plugging or repair is required-for degradation either (a) equal to or greater than 50% of the tube nominal wall thickness if the defect length is less than or equal to 0.55 inches; or (b) equal to or greater than 40% of the tube no'ninal wall thickness if the defect length is greater than 0.55 inches; or (c) equal to or greater than 40% of the tube nominal wall thickness if the defect is located in an area of reduced eddy current sensitivity (upper and lower tubesheet secondary faces and tube support plate entry and exit locations). The above plugging criteria for the primry side tube freespan apply only until Refueling Outage 6R, at which time the repair limit will be such a limit as has been approved by the NRC.
Where experience in similar plants with similar water chemistry, as documented by USNRC Bulletins / Notices, indicate critical areas to be inspected, at least 50% of the tubes inspected should be from these critical areas. First sanple inspections sanple size ny be modified subject to NRC review and approval.
4-82 Amendment No. 47, 86
GPU Nuclear Corporation U Nuclear
- eme::ceo o
s Middletown, Pennsylvania 17057 0191' 717 944-7621 TELEX 84 2386 Writer's Direct Dial Number February 4, 1986 6211-86 9013 Mr. Thonas A. Gerusky, Director Pa. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120
Dear Mr. Gerusky:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.153 Enclosed please find one copy of Technical Specification Change Request No.153 to Appendix A of the Operating License for Three Mile Island Nuclear Station, Unit 1.
This request was filed with the U.S. Nuclear Regulatory Corrmission on the above date.
Sincerely,
- (
I h
H.
. Hukill Director, TMI-l HDH/SM0/spb Enclosure GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporatton
GPU Nuclear Corporation tf Nuclear
- ers::r/8o o
Middletown, Pennsy! vama 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number February 4, 1986 5211-86-2013 Mr. Normn P. Hetrick, Chairen Board of County Comissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120
Dear Mr. Hetrick:
Enclosed please find one copy of Technical Specification Change Request Ho.153 to Appendix A of the Operating License for Three Mile Island Nuclear Station, Unit 1.
This request was filed with the U. S. Nuclear Regulatory Comission on the above date.
Sincerely, c
P H.
. Hukill Director, TMI-l HDH/SM0/spb Enclosure GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
GPU Nuclear Corporation U duclear
- or,te::l/8o e
s Middletown, Pennsylvania 17057 0196 717 944 7621 TELEX 84 2386 Writer's Direct Diai Number February 4,1986 5211-86-2013 Mr. Jay H. Kopp, Chairmn Board of Supervisors of Londonderry Township R. D. #1, Geyers Church Road Middletown, PA 17057
Dear Mr. Kopp:
Enclosed please find one copy of Technical Specification Change Request No.153 to Appendix A of the Operating License for Three Mile Island Huclear Station, Unit 1.
This request was filed with the U. S. Nuclear Regulatory Commission on the above date.
Si cerely,
<f
/
HU. Hukill Director, TMI-l HDH/Sf10/spb Erclosure l
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation