ML20137T087

Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria

ML20137T087
Person / Time
Site:	Sequoyah
Issue date:	04/09/1997
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20137T077	List: ML20137T073 ML20137T087
References
NUDOCS 9704150310
Download: ML20137T087 (4)

Text

. _ . - _ .

ENCLOSURE 1

\

i I

l Mark-uo coDV of 1Jnit 1 TS osae 3/d 4-7 l

l l

l 9704150310 970409 PDR ADOCK 05000527 PDR P

1

l l

REACTOR COOLANT SYSTEM g vEILLANCE RE00fREMENTS (Continued) l

' k'c,N~

shall

3. A tube inspection (pursuant to Specification 4.4.5.4.a.8) does be performed on each selected tube. If any selected tube i

l 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.

Indications left in service as a result of application of the tube T)

4. Rf18 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 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 Tne inspections include those portions of the tubes where ~

imperfections were previously found.

NOTE:

Tube degradation identified in the portion of the tube that a193 is not a reactor coolant pressure boundary (tube end up to the start of the tube-to-tubesheet weld) is excluded free the Result and Actics Required in Table 4.4-2.

4D '

d. Implementation of the steam generator tube / tube support plate repairM18 fJ criteria requires a 100 aercent bobbin coil inspection for hot-leg and cold-leg tube support pitte intersections down to the lowest cold-leg 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:

Catenary Insnaction Results Less than 55 of the total tubes inspected are degraded C-1 tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the totalor betw tubes inspected the total tubes inspected are defective, are degraded tubes.

More than 10% of the toth1 tubes inspected are degraded C-3 tubes or more than 15,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.

l g*g g

" Qa::t:d c5=;e tet{i: ps e are app'ic ] te Cycle B eperstica Amendment No, 189, 214 3/44-7 October 11, 1995 SEQUOYAH - UNIT 1

l ENCLOSURE 2 1

I l

l l

Retyped Unit 1 TS cane 3/4 4-7 l

i l

a 4

. REACTOR COOLANT SYSTEM

. 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 l 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.  !

I

c. The tubes selected as the second and third samples (if required by l Table 4.4-2) during each inservice inspection may be subjected to a i partial tube inspection provided:  !

l

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. l

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,