ML20207E626
| ML20207E626 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/26/1999 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20207E622 | List: |
| References | |
| NUDOCS 9903110024 | |
| Download: ML20207E626 (5) | |
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6 ATTAC'1 MENT TO LICENSE AMENDMENT NO.
4 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of citange.
Remove Insert i
3/4 4-14 3/4 4-14 3/4 4-14a 3/4 4-14a B 3/4 4-3 B 3/4 4-3 4
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l NPF-73 REACTOR COOLANT SYSTEM
' ' SURVEILLANCE REQUIREMENTS-(Continued) 3 '. -
A loss-of-coolant accident requiring actuation of ' the engineered safeguards, or 4.
A main steamline or feedwater line break.
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- i 4.4.5.4' Acceptance Criteria i
a.
As used.in this Specification:
1.
Impgrfection means an exception to the dimensions, finish or contour of a
tube or sleeve from that required by' fabrication._ drawings or specifications.
Eddy-current testing indications below 20 percent of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Dearadation means a service-induced cracking,
was' age, c
wear or general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Dearaded ' Tube means a
tube or sleeve containing imperfections greater than or equal to 20 percent of the nominal wall thickness. caused by degradation.
4.
Percent Dearadation means the percentage of the tube or sleeve wall thickness affected or_
removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a defect'is defective.
Any tube which does not permit the passage of the eddy-current inspection probe shall be' deemed a defective tube.
6.
Pluacina or ReDair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection.
The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:
a.
Original tube wall 40%
b.
ABB Combustion Engineering TIG welded sleeve wall 32%
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c.
Westinghouse. laser welded sleeve wall 25%
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BEAVER VALLEY - UNIT 2 3/4 4-14 Amendment No.
.. -. ~.
NPF REACTOR COOLANT SYSTEM StfRVEILLANCE REQUIREMENTS.(Continued)
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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, or a steamline l
or.feedwater line break as specified in 4.4.5.3.c, above.
' 8.
Tube Inspection' means an inspection of the steam generator tube from the point of entry (hot leg side) completely'around the U-bend to the top support to the cold leg.
9.
Tube Renair refers to sleeving. which 1.s used to maintain a tube in-service or return a tube to service.
This includes the removal.of plugs that were installed as a corrective or preventive measure.
The following sleeve designs have been found acceptable:
a)
ABB Combustion Engineering TIG welded sleeves, CEN-629-P, Revision 02 and CEN-629-P Addendum 1.
b)
Westinghouse laser welded
- sleeves, WCAP-13483, Revision 1.
b.
The steam generator shall be determined OPERABLE after completing. the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit) required by Table 4.4-2.
4.4.5.5 Reports a.
Within 15. days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be submitted in a Special Report in accordance with 10 CFR 50.4.
b.
The complete results of the steam generator tube and sleeve ins,ervice inspection shall be submitted in a Special Report in accordance - with 10 CFR 50.4 within 12 months following the completion of the inspection.
This Special Report shall include:
1.
Number ~and extent of-tubes and sleeves inspected.
l BEAVER VALLEY.- UNIT 2-3/4'4-14a Amendment No.
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17.
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'NPF-73.
REACTOR COOLANT SYSTEM BA'SES-
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'3/4.4.5' STEAM GENERATORS fContinued)
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, d e c a y.' h e a t. r e m o v a l ' c a p a b i l i t i e s for RCS temperatures greater than 350'Fs if one steam generator becomes. inoperable due to single failure considerations.
Below 3 50"F,
decay heat. is removed by. the RHR l
system.
1 The ' Surveillance Requirements for inspection of the steam generator l tubes ensure thot 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 l
essential in order to maintain. surveillance of the conditions of the-I 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 l
steam generator,tubinga also.provides.a means of characterizing _ the l
nature and cause of any tube degradation so that corrective measures i
can be taken.
The plant is expected to be operated in a manner such that the l
secondary coolant will be maintained within those parameter limits i
found:to result'in negligible corrosion of the steam generator tubes.
'If the ; secondary coolant chemistry 'is not maintained within these i
parameter limits, localized corrosion may likely result in stress j
corrosion cracking.
.The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant System (primary _ to secondary LEAKAGE 500 gallons per day per @.eam
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- generator).
Cracks having a primary to secondary LEAKAGE less than this limit during operation will have an adequate margin of safety to withstand _the loads imposed during normal operation and by postulated accidents.
Operating' plants have demonstrated that primary to secondary LEAKAGE of 500 gallons per day per steam generator can readily. be detected by radiation monitors-of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired by sleeving._
The technical - bases for sleeving-are described in the approved vendor reports _ listed in Surveillance Requirement 4,4.5.4.a.9.
L Wastage-type defects are unlikely with the all volatile treatment I
' ( AVT) - of secondary coolant.
However, even if a defect of similar type should develop in service, it will be found during scheduled l-inservice steam generator tube examinations.
Plugging or repair will be required-of. all. tubes with imperfections ~ exceeding the plugging or repair limit.
Degraded steam generator tubes may be L
i BEAVER VALLEY - UNIT 2_
B 3/4 4-3 Amendment No.
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ATTACEMENT B Beaver Valley Power Station, Unit No. 2 Change Summary P
I Tyned Paces Editorial Chances 3/4 4-14 No additional changes are included.
3/4 4-14a This page will be changed in an amendment to
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be issued in response to License Amendment Request-(LAR) No. 116 prior to issuing the amendment for this LAR; therefore, this page i
has been updated to include the LAR No. 116
]
changes.
Page 3/4 4-14b was previously included in the final typed pages due to shifting information from page 3/4 4-14a; however, no change to this page is now required since the amendment for LAR No. 116 will issue this page with no additional changes required.
1 B 3/4 4-3 No additional changes are included.
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