ML20128M482

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Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage
ML20128M482
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/08/1996
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML19355E456 List:
References
NUDOCS 9610160101
Download: ML20128M482 (17)
v • d • e


Text

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Unit 2 Technical Specification Pages for L* Repair Criteria and Deletion of Cycle-Specific L' b

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l 9610160101 961008 "-

PDR I P-ADOCK 05000364 PDR- -

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Unit 2 Technical Specification Page Markups for L* Repair Criteria and Deletion of Cycle-Specific L*

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REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

. ACTION:

1 With one or more steam generators inoperable, restore the inoperable  !

] generator (s) to OPERABLE status prior to increasing Tavg above 200*F.  !

SURVEILLANCE REQUIREMENTS  !

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4.4.6.0 Each steam generator shall be demonstrated OPERABLE Dy performance of the following augmented inservice inspection program and the requirements )

of Specification 4.0.5.

4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam I generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table l 4.4-1.

4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4.

The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators. Selection of tubes to be inspected is not af fected by the F*/L* designation. When applying the l exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous defects or imperfections in the area repaired by sleeving are not considered an area 3 requiring re-inspection. The tubes selected for these inspections shall be '

selected on a random basis except:

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a. Where experience in similar- plm.:ts; wiNi similar water chemistry  ;

indicates critical areas to be inspected, then at least 50s of the j tubes inspected shall be from these critical areas. 1

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1. All nonplugged tubes that previously had detectable wall penetrations greater than 20%.
  1. When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.6.4.a.9.

s# L' criteric ic applicabic tc Cycle 11 cr.ly. l EARLEY-UNIT 2 3/4 4-9 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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 act more than is 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 or sleeves must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

4.4.6.2.2 Steam Generator F*/L*,9 Tube Inspection - In addition to the l minimum sample size as determined by Specification 4.4.6.2.1, all F*/L* tubes will be inspected within the tubesheet region. The results of this inspection will not be a cause for additional inspections per Table 4.4-2.

4.4.6.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. 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 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 maximum of once per 40 months.
b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month 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 4.4.6.3.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 first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

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"" L* Criteria de applicable te Cycle 11 cr.ly. l FARLEY-UNIT 2 3/4 4-11 AMENDMENT NO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

6. Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L*

criteria. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service by plugging. Tnis definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.6.4.a.16 l for the repair limit applicable to these intersections.

7. Unserviceable describes the condition of a tube or sleeve 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 l feedwater line break as specified in 4.4.6.3.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 of the cold leg. For a s tube that has been repaired by sleeving, the tube inspection i should include the sleeved portion of the tube.

9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, which is 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.

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    1. L' Criteri: i: applicable to Cycle 11 caly.

FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

- . - - = . - - - - - - _ ~ . . - - - . .. -. - . .-

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
10. Preservice Inspection means an inspection of the full length of each 1

tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections,

11. F* Distance is the distance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist i pullout of the tube from the tubesheet. The F* distance is equal to )

j 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the roll transition, whichever is lower in elevation. The allowance for )

' eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

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12. F* Tube is a tube:

f a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to .

20% of nominal wall thickness within the F* distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be j applied or the tube must be plugged or repaired.

i Insert A i

12. 1.' Lengthu is the length of th: npanded p;: tion cf the tube into the tub ch::t frer the better of th: ::lled tz:ncition :: the top cf th tub: ch::t, *ich ever 1: 1 w :, that h:: been determined te be 1. 05 inch::.

q 14 L' Tub: u; c) i: tub: .ith deg dation aquel : g ::ter than 005 beleu the L' length and not deg d:d within the L* length; b) th: cddy

, eur:cnt indicatier of deg :dation beleu the L' length must be determined te be the-::: ult of :: ch: .:ith an : icnt: tion no g ::::: than 15 deg ::: f::: :nicl; c) the L' ::iteri: ch ll be limited tc a m: Mire of j

, 600 tub: nd: pc tcar genc :ter; di tube: qu lifying :: F' tub : see '

4 not ule::ified c: L' tube:; c) minimur 'f O 3.1 inche: cf the tub: int:

. the tubech::t f::: the top cf tube h :t :: better of th: :clled

't beansiti n, ,;ich :v:: i: louer, ch:11 he in:pceted u ing ::baefag b5  % Ew w 6 5 e a w s w sv w a v' w give equiva.:nt :: better informaticr en the crientation and length of Miel ::: 50; f) minimur agg gst: cf 2.07 inch:: Of cound : kk expanelem te ; maximur :::ch length of .30 inch::; F a maximur cf 5 distinct hhskeation: with : : ingle band of tube deg:cdcti n; and i) chat f  : mcin; in :::vice.

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"" L' Criteria i: applic ble t: Cycle 11 only.

j FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

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.I REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.5 Reports

a. Following each inservice inspection of steam. generator tubes, the  !

number of tubes plugged, repaired or designated F*/L* in each steam generator shall be reported to the Commission within 15 days of the coreletion of the inspection, plugging or repair effort.

b. The complete results of the steam generator tube and sleeve  !

inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months i following the completion of the inspection. This Special Report 4

shall include:

1. Number and extent of tubes and sleeves inspected.
2. Location and percent of wall-thickness penetration for each indication of an imperfection.

) 3. Identification of tubes plugged or repaired.

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c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report sha.1 provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

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d. For implementation of the voltage-based repair criteria to tube l support plate intersections, notify the staff prior to returning the steam generator to service (Mode 4) should any of the following conditions arise:
1. If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leak limit (determined from the licensing basis dose calculation for the postulated main steam line break) for the next operating cycle.
2. If circumferential crack-like indications are detected at the tube support plate incersections.
3. If indications are identified that extend beyond the confines of the tube support plate.
4. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.
5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the  !

actual , measured end-of-cycle) voltage distribution exceeds  !

l x 10', notify the NRC and provide an assessment of the safety significance of the occurrence.

  1. " L' Critcric ic applicabic tc Cycic 11 calyr FARLEY-UNIT 2 3/4 4-13b AMENDMENT NO. .

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REACTOR COOLANT SYSTEM BASES
3. The tube plugging limit continues to apply to the portion of the l tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.

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4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
b. Laser Welded
1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.
2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.
3. At the weld joint, degradation must be evaluated in both the sleeve and tube.
4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.

S. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1,54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.

L* is similar to F*; however, bands of axial degradation are allowed as long

.as sufficient non-degraded tubing is available to ensure structural and leakage integrity. L' criterier i: cr.ly applicabir fer Unit Cycle 11.

Precided bel a i: the Unit 2 Cycle 11 specific L' c ri t e rier. ; The I* distance for a single band of degradation is 1. 74 inches and for two hands of degradation is 1. 87 inches. Eddy current uncertainty measurement allowance must be added to these I* distances. The ~^ v"~ length for any degradation band is 0.5 inches. SNC has administratively limited the number of distinct degradation areas in the band to 15, although Westinghouse support documentation justifL' es gp to 30 such areas.

FARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO. l

. ~. - .- _.. - - - . . .- - . .

REACTOR COOLANT SYSTEM BASES Unit 2 Cycle 11 Opecific L' critorien Pc:creter vehe Hi*Muen-die"6 2.07 ineh:

Maximur number of dictinct degradction crec: ir a band &

Heximur inclir tion angle .ithir a single bcad 15 degeeee Mcximur ::cch length .39 inch:

Minimum dietan : Of S"E f Or the better Of the t:cncition 1.05 inche:

ecil te the top of the indication Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 20%

of the original' tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10 CFR 50.73 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy- l current inspection, and revision to the Technical Specifications, if '

necessary. I l

l EARLEY-UNIT 2 B 3/4 4-3c AMENDMENT NO. l

Insert A

13. L* Length is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the tube sheet, which ever is lower, that has been determined to be .5 inches plus allowance for eddy current measurement uncertainty. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.
14. L* Tube: a) is a tube having degradation equal or greater-than 40% through wall that is below the L* 1ength and not degraded within the L* 1ength; b) the eddy current indication of degradation below the L* 1ength must be determined to be the result of cracks with an orientation no greater thar 30 degrees from axial; c) the L* criteria shall be limited 2 a maximum of 600 tube ends per steam generator; d) tubes qualifying as F* tubes are not classified as L* tube-; el a minimum of 3.1 inches of the tube into the tubet.ieet from the top of tubesheet or bottom of the rolled transition, which ever is lower,'shall be inspected using rotating pancake coil eddy current technique or an inspection method.shown to give equivalent or better information on the orientation and length of axial cracks; f)'a minimum aggregate of 1.74 inches plus allowance for eddy current measurement uncertainty, of sound roll expanded tube distance with no more.than 1 band of tube degradation j in the form of axial cracking (15 flaws in a band of 0.5 l inch or less in axial length), which is limited to flaws of ,

less than 30 degrees froca the axial direction, must be found in the inspected portion of the tube; or a minimum aggregate of 1.87 inches plus allowance for eddy current measurement uncertainty, sound roll expanded tube distance with no more than 2 bands of tube degradation in the form of axial l cracking (15 flaws in a band of 0.5 inch or less in axial length) separated by at least 0.5 inch.of sound roll expansion, which is limited to flaws of less than 30 degrees from the axial direction, must be found in the inspected portion of the tube; and g) that remains in service. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

Unit 2 Technical Specification Pages Replacement Pages for L* Repair Criteria and Deletion of the Cycle-Specific L*

Page 3/4 4-9 Replace Page 3/4 4-11 Replace Page 3/4 4-12a Replace Page 3/4 4-12b Replace Page 3/4 4-13b Replace Page B 3/4 4-3b Replace Page B 3/4 4-3c Delete l

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RZACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing Tavg above 200*F.

SURVEILLANCE REQUIREMENTS 4.4.6.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

l 4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam l generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4.

The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators. Selection of tubes to be inspected is not affected by the F*/L* designation. When applying the l exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring re-inspection. The tubes selected for these inspections shall be selected on a random basis except:

a. Where experience in similar plantr with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1. All nonplugged tubes that previously had detectable wall penetrations greater than 20%.
  1. When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.6.4.a.9.

I FARLEY-UNIT 2 3/4 4-9 AMENDMENT NO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Category Inspection Fesults 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 total tubes inspected are defective, or between 54 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 or sleeves must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

4.4.6.2.2 Steam Generator F*/L* Tube Inspection - In addition to the l minimum sample size as determined by Specification 4.4.6.2.1, all F*/L* tubes will be inspected within the tubesheet region. The results of this inspection will not be a cause for additional inspections per Table 4.4-2.

4.4.6.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. 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 consecutive inspections followina 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 i and no additional degradation has occurred, the inspection l interval may be extended to a maximum of once per 40 months. l
b. If the results of the inservice inspection of a steam generator l conducted in accordance with Table 4.4-2 at 40 month intervals i 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 4.4.6.3.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 first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

l FARLEY-UNIT 2 3/4 4-11 AMENDMENT NO.

I REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

6. ,?luqqing or Repair Limit means the imperfection depth at or F eyond which the tt Je shall be repaired (i.e., sleeved) or removed from servii:e by plugging and is greater than or equal to 40s of the nominal tube wall thickness. This definition does not apply for tubes that meet the F*/L* l criteria. For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the sleeve between the weld joints requires the tube to be removed from service by plugging. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.1.6.4.a.16 for the repair limit applicable to these intersections.
7. Unserviceable describes the condition of a tube or sleeve 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 4.4.6.3.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 of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.
9. Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse report WCAP-12672, which is 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.

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FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO.

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_ _ . _ - - . =- = - -

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
11. F* Distance is the distance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist pullout of the tube from the tubesheet. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tube sheet or the bottom of the roll transition, whichever is lower in elevation. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.
12. F* Tube is a tube: a) with degradation equal to or greater than 40%

below the F* distance, and b) which has no indication of imperfections I greater than or equal to 20% of nominal wall thickness within t e F*

distance, and c) that remains inservice.

If the above criteria cannot be met, then the L* tube criteria may be  !

applied or the tube must be plugged or repaired.

13. L* Length is the length of the expanded portion of the tube into the tube sheet from the bottom of the rolled transition or the top of the tube sheet, which ever is lower, that has been determined to be .5 inches plus allowance for eddy current measurement uncertainty. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.
14. L* Tube: a) is a tube having degradation equal or greater than 40%

through wall that is below the L* length and not degraded within the L*

length; b) the eddy current indication of degradation below the L*

length must be determined to be the result of cracks with an orientation no greater than 30 degrees from axial; c) the L* criterie shall be limited to a maximum of 600 tube ends per steam generator; d) tubes qualifying as F* tubes are not classified as L* tubes; e) a minimum of 3.1 inches of the tube into the tubesheet from the top of tubesheet or bottom of the rolled transition, which ever is lower, shall be inspected using rotating pancake coil eddy current technique t 9n inspection method shown to give equivalent or better information on the orientation and length of axial cracks; f) a minimum aggregate of 1.74 inches plus allowance for eddy current measurement uncertainty, of sound roll expanded tube distance with no more than 1 band of tube degradation in the form of axial cracking (15 flaws in a band of 0.5 inch or less in axial length), which is limited to flaws of less than 30 degrees from the axial direction, must be found in the inspected portion of the tube; or a minimum aggregate of 1.87 inches plus allowance for eddy current measurement uncertainty, sound roll expanded tube distance with no more than 2 bands of tube degradation in the form of axial cracking (15 flaws in a band of 0.5 inch or less in axial length) separated by at least 0.5 inch of sound roll expansion, which is limited to flaws of less than 30 degrees from the axial direction, must be found in the inspected portion of the tube; and g) that remains in service. The allowance for eddy current uncertainty is documented in the steam generator eddy current inspection procedure.

FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.

5 REACTOR COOLANT SYSTEM E

SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.5 Reports a.

Following each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated F*/L* in each l steam generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort.

b. The complete results of the stesm generator tube and sleeve
inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include

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1. Number and extent of tubes and sleeves inspected.
2. Location and percent of wall-thickness penetration for each indication of an imperfection.

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3. Identification of tubes plugged or repaired.
c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be

! reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

d. For implementation of the voltage-based repair criteria to tube support plate intersections, notify the staff prior to returning the steam generator to service (Mode 4) should any of the following conditions arise:

t

1. If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) vcitage distribution exceeds the leak limit (determined from l the licensing basis dose calculation for the postulated main steam line break) for the next operating cycle.
2. If circumferential crack-like indications are detected at the tube support plate intersections.

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3. If indications are identified that extend beyond the confines of the tube support plate.
4. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

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5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual , measured end-of-cycle) voltage distribution exceeds 1 x 10", notify the NRC and provide an assessment of the safety significance of the occurrence.

i FARLEY-UNIT 2 3/4 4-13b AMENDMENT NO.

. _ . .. . - _ .m _ . . _ _ _ _ _ _ . __ _ . - _ _ . _ _ . __-_ _

REACTOR COOLANT SYSTEM BASES

3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to these areas also.
4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
b. Laser Welded
1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.
2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.
3. At the weld joint, degradation must be evaluated in both the sleeve and tube.
4. In a joint with more than one weld, the weld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.
5. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1,54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.

L* is similar to F*; however, bands of axial degradation are allowed as long  !

as sufficient non-degraded tubing is available to ensure structural and leakage integrity. The L* distance for a single band of degradation is 1.74 inches and for two bands of degradation is 1.87 inches. Eddy current uncertainty measurement allowance must be added to these L* distances. The '

maximum length for any degradation band is 0.5 inches. SNC has administrative 1y limited the number of distinct degradation areas in the band to 15, although Westinghouse support documentation justifies up to 30 such areas.

Steam generator tube inspections of operating plants have demonstrated the I capability to reliably detect wastage type degradation that has penetrated 20%

of the original tube wall thickness, j Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10 CFR 50.73 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a

' requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision to the Technical Specifications, if necessary.

l FARLEY-UNIT 2 B 3/4 4-3b AMENDMENT NO. l l

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i Attachment 3 4

Westinghouse Af11 davit CAW-96-988 1

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