ML20137T087
| ML20137T087 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/09/1997 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20137T077 | List: |
| References | |
| NUDOCS 9704150310 | |
| Download: ML20137T087 (4) | |
Text
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ENCLOSURE 1
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Mark-uo coDV of 1Jnit 1 TS osae 3/d 4-7 l
9704150310 970409 PDR ADOCK 05000527 PDR P
REACTOR COOLANT SYSTEM g vEILLANCE RE00fREMENTS (Continued) l
' k'c,N~
A tube inspection (pursuant to Specification 4.4.5.4.a.8) does shall 3.
be performed on each selected tube. If any selected tube not permit the passage of the eddy current probe for a tube i
inspection, this shall be recorded and an adjacent tube shall l
be selected and subjected to a tube inspection.
T)
Indications left in service as a result of application of the tube Rf18 support plate voltage-based repair criteria shall be inspected by 4.
bobbin coil probe during all future refueling outages.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a c.
partial tube inspection provided:
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were 1.
previously found.
Tne inspections include those portions of the tubes where 2
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imperfections were previously found.
Tube degradation identified in the portion of the tube that is not a reactor coolant pressure boundary (tube end up to a193 NOTE:
the start of the tube-to-tubesheet weld) is excluded free the Result and Actics Required in Table 4.4-2.
4D Implementation of the steam generator tube / tube support plate repairM18 criteria requires a 100 aercent bobbin coil inspection for hot-leg and d.
f cold-leg tube support pitte intersections down to the lowest cold-leg J
tube support plate with knoci outside diameter stress corrosionThe cracking (005CC) indications.
l tube support plate intersecties having 005cc indication i
tubes inspected over their full length, The results of each sample inspection shall be classified into one of the following three categories:
Insnaction Results Catenary Less than 55 of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-1 One or more tubes, but not more than 1% of the totalor betw C-2 tubes inspected are defective, degraded tubes.
the total tubes inspected are More than 10% of the toth1 tubes inspected are degraded tubes or more than 15,of the inspected tubes are C-3 defective.
In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to Note:
be included in the above percentage calculations.
Qa::t:d c5=;e tet{i: ps e are app'ic ] te Cycle B eperstica l g*g g Amendment No, 189, 214 3/44-7 SEQUOYAH - UNIT 1 October 11, 1995
l ENCLOSURE 2 1
l Retyped Unit 1 TS cane 3/4 4-7
a 4
. SURVEILLANCE REQUIREMENTS (Continued) 3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
4.
Indications left in service as a result of application of the tube support plate voltage-based repair criteria shall be inspected by bobbin coil probe during all future refueling outages.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a i
partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections include those portions of the tubes where imperfections were previously found.
NOTE: Tube degradation identified in the portion of the tube that is not a reactor coolant pressure boundary (tube end up to R193
]
the start of the tube-to-tubesheet weld) is excluded from the i
Result and Action Required in Table 4.4-2.
d.
Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to the l
lowest cold-leg tube support plate with known outside diameter i
stress corrosion cracking (ODSCC) indications. The determination of the lowest cold-leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a f
20 percent random sampling of tubes inspected over their full i
length.
The results of each sample inspection shall be classified into one of the following three categories:
Cateoorv Insoection Results C-1 Less than 5% of the total tubes inspected are j
degraded tubes and none of the inspected tubes J
are defective.
C-2 One or more tubes, but not more than 1% of the total 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 degraded tubes or more than 1% of the inspected tubes are defective.
Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
SEQUOYAH - UNIT 1 3/4 4-7 Amendment No. 189, 214,