ML20206B472

Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F

ML20206B472
Person / Time
Site:	Farley
Issue date:	04/21/1999
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20206B443	List: ML20206B439 ML20206B472
References
NUDOCS 9904290256
Download: ML20206B472 (17)

Text

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Programs and Manuals 5.5

. 5.5 Programs and Manuals 5.5.9.2.1 (continued)

.. ,d. Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent i bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to the lowest cold-

[ Unit 2 only j i leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications.

The determination of the lowest cold leg tube f

support plate intersections heWg ODSCC indications shall be based on Gw performance of at least a 20 percent random sampling of tubes I inspected over their fulllength.

I eThresults of each sample inspection shall be l

classified into one of the following three categories:

I inspection Raoults Category C-1 Less then 5% of the total tubes

inspected are degraded tubes and none of theinspected tubes are defecthe. '{

l C-2 One or more tubes, but not more i

f then 1% of the totaltubes inspected are defective, or between i

5% and 10% of the totaltubes inspected are dearaded tubes.

C-3 More than 10% of the totaltubes inspected are degraded tubes or

. more than 1% of theinspected tubes are defecthe.

No inspections, previously degraded tubes

• e :te: In exhibit significant (greater than

'::n ust 10%) further well penetrations to be included in the i abov. perceninge caicuistions.

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[ Unit 2 only: or sleeves]

(continued)

Farley Units 1 and 2 5.5-8 Amendment No. (Unit 1)

AmendmentNo. (Unit 2) 9904290256 990421 '

PDR ADOCK 05000348 $

P PDR ,]

Enclosure 2 _

Joseph M. Farley Nuclear Plant Steam Generator Replacement Related Technical Specifications Change Request Revision 1 to December 1,1998 Submittal Corrected Typed Pare for Unit 1 SGR TS Submittal

L Programs and Minuits 5.5 5.5 Programs and Manuals 5.5.9.2.1 (continued)

d. (Unit 2 only] Implementation of the steam generator l tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and j cold-leg tube support plate intersections down to l the lowest cold-leg tube support plate with known I I

outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold leg tube support plate intersections having ODSCC indications shall be based on the i performance of at least a 20 percent random

sampling of tubes inspected over their full length.

The results of each sample inspection shall be classified into one of the following three categories:

Category inspection Results l C-1 Less than 5% of the total tubes  ;

inspected are degraded tubes and none i

l of the inspected tubes are defective.

l _ .

C-2 One or more tubes, but not more than l 1% of the total tubes inspected are I defective, or between 5% end 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

[ Unit 2 only; or sleeves) must exhibit significant (greater l than 10%) further wall penetrations to be included in the above percentage calculations.

(continued)

Fariey Units 1 and 2 5.5-8 Amendment No. (Unit 1)

Amendment No. (Unit 2)

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Enclosure 3 -

, Joseph M. Farley Nuclear Plant i Steam Generator Replacement Related Technical Specifications Change Request Revision 1 to December 1,1998 Submittal l

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Corrected Markun Pares for Unit 2 SGR TS Submittal I

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, Programs and Manuals 5.5 l

5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued) 5.5.9.1,. Steam Generator Sample Selection and inspection Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 5.5.9-1.

5.5.9.2 Steam Generator Tube pie Selection and Inspection 5.5.9.2.1 The steam generator tube minimum sample size, inspection resu!t classifloation, and the corres nding action required shall be as specdled in Tab .5.9-2

M 51TThe insonnce inspection of steam generator tubes shall be performed at the frequencies specified in Specification 5.5.9. and the inspected tubes shall be vertfled kthe acceptance critena cf Speedication 5.5.9.4. The tubes selected for each inservice inspection shen include at least 3% of the total number of tubes in au steem generators. For h

Unit 2 only: Selection of tubes to be inspeciso es not affected by the F* designation.) When applying the exceptions of 5.5.9.2.s through 5.5.9.2.c, previous defects or imperfedians in the ar6e repaired by sleeving ~

are not considered an ares requiring reinspection.5The tubes selected for these inspections shen be selected on a random basis exmh

a. Where exponence in sWier plants with similar water chemistry indicsms critical areas to be inspected, then at Iret 50% of the tubes inspected shot be from theore critical areas.

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspechon) of each steem generator shall include:

1. All nonplugged tubes that provicusly had detectable wsN penetrations greater than 20%.

" When refemng to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 5.5.9.4.a.9. l (continued)

Fariey Units 1 and 2 5.56 Amendment No. (Unit 1)

Amendment No. (Unit 2) s

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Programs and Manutls 5.5 5.5 Programs and Manuals 5.5.9.2.1 (continued)

. d. Implementation of the steam generator tube 4ube support plate repair criteria requires a 100 percent I bobbin coil inspecbon for hot-leg and cold-leg tube

' support plate interseebons down to the lowest ccid-leg tube support plate with known outside diameter 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 20 percent random sampling of tubes t inspected over their fulllength.

' ^#

The results of each sa vnple inspection shall be I classified into one of thw following three categories:

j Category inspection stesults i I C-1 Less than 5% of the total tubes inspected are do w W tubes and I

none of theinspected Lhos are

, I defective ~

" ' One ormore tubes, but not more C-2 8

e than 1% of the totaltubes 8

inspected are defective, or between 5% and 10% of the totaltubes inspected are dooraded tubes.

C-3 More than 10% of the total tubes inspected are degeded tubes or more than 1% of theinspected tubes are defective.

l p::in e i =allmust inspections, previously exhibit significant degraded (greater than tubes '

10%) further wall penetrations to be included in the above percentage calculations.

4 (continued)

Farley Units 1 and 2 5.54 Amendment No. (Unit 1)

. AmendmentNo. (Unit 2)

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Enclosure 4 Joseph M. Farley Nuclear Plant Steam Generator Replacement Related Technical Specifications Change Request R.evision 1 to December 1,'1998 Submittal Corrected Typed Panes for Unit 2 SGR TS Submittal i

i i

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i Progrcms cnd Minurls l

5.5 l

l 5.5 Programs and Manuals l 5.5.9 Steam Generator (SG) Tube Surveillance Prooram (continued) 5.5.9.1 Steam Generator Sample Selection and Inspection Each steam generator shall be determined OPERABLE during

! shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 5.5.9-1.

5.5.9.2 Steam Generator Tube Samole Selection and Inspection l l The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as l specified in Table 5.5.9-2. The inservice inspection of steam l generator tubes shall be performed at the frequencies specified in Specification 5.5.9.3, and the inspected tubes shall be verified l acceptable per the acceptance criteria of Specification 5.5.9.4. The l tubes selected for each inservice inspection shall include at least 3%

of the total number of tubes in all steam generators. The tubes l selected for these inspections shall be selected on a random basis except l a. Where experience in similar plants with similar water chemistry l indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.

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' b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shallinclude:

1. All nonplugged tubes that previously had detectable wall penetrations greater than 20%.

2. Tubes in those areas where experience has indicated l potential problems, i

l 3. A tube inspection (pursuant to Specification 5.5.9.4.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.

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c. The tubes selected as the second and third samples (if required by Table 5.5.9-2) during each inservice inspection may be l subjected to a partial tube inspection provided:

1 (continued)

Farley Units 1 and 2 5.5-6 Amendment No. (Unit 1)

Amendment No. (Unit 2)

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• Progrrms cnd M:nutls l 5.5 5.5 Programs and Manuals 5.5.9.2 Steam Generator Tube Samole Selection and Inspection (continued)

1. The tubes selected for these samples indude the tubes i l

from those areas of the tube sheet array where tubes with j imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

I

, The results of each sample inspection shall be dassified into one of I the following three categories:

Category inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the l total tubes inspected are defective, or between 5%

l and 10% of the total tubes inspected are degraded l 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 inspechons, previously degraded tubes must exhibit l significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

1 5.5.9.3 inE+%n Freouencies l The above required inservice inspections of steam generator tubes l shall be performed at the following frequencies:

l

a. The first inservice inspection shall be performed after 6 l Effective Full Power Months but within 24 calendar months of initial cnbcality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two l consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a i maximum of once per 40 months. ,

(continued) 1 1

Farley Units 1 and 2 5.5-7 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Programs tnd Manurls 5.5 5.5 Programs and Manuals 5.5.9.3 Inspection Freauencies (continued)

b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 5.5.9-2 at 40 month l intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.9.3.a; the interval may then be extended to a maximum of once per 40

. months.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the  : 7 first sample inspection specified in Table 5.5.9-2 during the l shutdown subsequent to any of the following conditions:

1. Primary-to-secondary tube leaks (not including leaks originating from tube-to-tubesheet welds) in excess of the limits of Specificaten 3.4.13.

2. A seismic occurrence greater than the Operating Basis Earthquake.

3. ' A loss-of-coolant accident requiring actuation of the engineered safeguards. .

4. A main steam line or feedwater line break.

5.5.9.4 Acceptance Cnteria

a. As used in this Specification:

1. lmoerfection means an exception to the dimensions, finish or contour of a tube from that required by l fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall thickness, if detectable, may be considered as imperfections.

2.

Dearadation means a service-induced cracking,

wastage, wear or general corrosion occurring on either inside or outside of a tube. l

3. Dearaded Tube means a tube that contains l imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.

(continued)

Farley Units 1 and 2 5.5-8 Amendment No. (Unit 1)

Amendment No. (Unit 2) t ..I . . . . .

i Progrtms End Minut!s 5.5 5.5 Programs and Manuals 5.5.9.4 Accest.nce Criteria (continued)

4.  % Dearadation means the percentage of the tube wall l thickness affected or removed by degradation.

5. Defect means an imperfecbon of such severity that it exceeds the plugging limit. A tube containing a defect l

. is defective.

6.

• Pluaaina or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from l service by plugging and is greater than or equal to 40%

of the nominal tube wall thickness. l  :

7. Unserviceable describes the condition of a tube if it l leaks or contains a defect large enough to affect its structuralintegrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 5.5.9.3.c, above.

. 8. Tube inspechon means an inspection of the steam generator tube from the point of entry (hot leg side) ccT-;':t'y around the U-bend to the top support of the cold leg.

9. Preservice Inspection means an inspechon of the full length of each tube in each steam generator performed by oddy cu Tent techniques prio. to service to establish a baseline condition of the tubing. This inspechon shall be performed using the equipment and techniques l

. expected to be used during subsequentinservice inspechons.

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b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit) required by Table 5.5.9-2.

4 Farley Units 1 and 2 5.5-9 Amendment No. (Unit 1)

Amendment No. (Unit 2)

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Enclosure 5 Joseph M. Farley Nuclear Plant Steam Generator Replacement Related Technical Specifications Change Request Revision 1 to December 1,1998 Submittal Corrected Pare for NSSS Licensing Report l

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. Table 2.1-3 Class 1 RCL Piping ASME Stress Actual versus Allowable- Equation 9 Eq. 9") Design Eq. 90) Design Eq. 9") Faulted Eq. 90) Faulted Maximum Allowable Maximum Allowable (ksi) (ksi) (ksi) (ksi) _

Hot Leg 19.4 26.7 39.5 53.4 Crossover Leg 17.8 24.0m 26.5 48.0G)

Cold Leg 15.7 26.7 31.5 53.4

)

U.2 tag (1) Equation 9 from ASME Code, Section 3, NB-3650 i (2) This allowable RCL piping stress is the lesser of the existing and the RSG outlet replacement elbows.

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Table 2.1-4 Steam Generator and Reactor Coolant Pump Support Structure Percentage of Allowable Stresses for Normal, Upset, and Faulted Conditions ,

Normal Upset Faulted Support Component (%) (%) (%)

Steam Generator Columns 34 44 92

)

Steam Generator Lower Bumpers 0 31 23 Steam Generator Upper Bumpers 0 18 18 Reactor Coolant Pump Columns 30 31 42 Reactor Coolant Pump Tie Rods 0 26 36 WCAP-15098 oM352-2. doc-022399 2.1-10 l