ML20107J162

Proposed Tech Specs Re SG F*

ML20107J162
Person / Time
Site:	Farley
Issue date:	04/22/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20107J154	List: ML20107J152 ML20107J162
References
NUDOCS 9604240357
Download: ML20107J162 (7)

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• l Enclosure 3 Joseph M. Farley Nuclear Plant Steam Generator Fa Technical Specification Changes Page Change Instructions Unit 2 Remove Page B_eplace Page 3/4 4-12b 3/4 4-12b B 3/4 4-3a B 3/4 4-3b l

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9604240357 960422 PDR ADOCK 05000364 P PDR

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

11. F* Distance is the discance 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 tubesheet or the bottom of the roll transition, whichever is lower in elevation.

12. F* Tube is a tubes 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.

] 13. Tube Exoansion is that portion of a tube which has been increased in diameter by a rolling process such that no crevice exists between the outside diameter of the tube and the hole in the tubesheet.

14. Tube Sucoort Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominately

, axially oriented outside diameter stress corrosion '

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cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair ILmit is based on maintaining steam generator tube

serviceability as described below

a. Steam generator tubes, whose degradation is I attributed to outside diameter stress corrosion i cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit (2.0 volts), will be allowed to remain in service.

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Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than the lower voltage repair limit [2.0 volts), will be repaired or plugged except as noted in 4.4.6.4.a.14.c below. ,

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

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4 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 i 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 2 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 i

of the sleeve represents the joint to be inspected and the lLait of the sleeve inspection.

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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 i 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 i of the tubesheet or the bottom of the roll transition, whichever is lower I j in elevation.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 1

20% of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection 4 f all into category c-3, these results will be reported to the commission l 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, j additional addy-current inspection, and revision to the Technical specifications, if necessary.

FARLEY-UNIT 2 B3/4 4-3b AMENDMENT NO.

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Enclosure 4 Joseph M. Farley Nuclear Plant Steam Generator F*

Technical Specification Changes Marked -Un Pages i

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. m : u :e:2 m m m SURVIII.IMCE REQUIRD(INTS Icontinued)

10. Preservice'!nspection leeans an inspection of the full length of each tube in each steam generater perferned by eddy current techniques prior to service to establish a baseline conditica of the tubing. This inspection ,shall be performed after the field hydrostatie test and prior to taltial pcutA 0FEAATICW using the equipshant and techniques expected to be used during subsequent inservice inspectierts.

M* Distance is the distance of the expanded pertio at~ ch provides a sufficient length See'bsed A. tube expansion aalat pu11eut .

graded tube frou the tubesheet. The F* dista equal to 1.19 inches and is measured d ye4 e top of sheet er the fAfrs' roll transition, whichever is be

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12. F* Tube is a tube:

al with degradation equal te er greater than 400 below

' the F* distance, and b) which has no indication of imperfections greater thaa er equal to 200 of nominal well thiekness within the F' distance, and c) that l remains inservice.

13. Tube Empansion is that parties of a tube which has been '

lacreased in diameter by a rolling process such that no crevise saists between the outside diameter of ths tube and the hele in the tubesheet.

14. Tube support Plate Fluccine Limit is usN for the disposities of a steam generator tube for continued

service that is experiencing outside diameter stress cerrosies cracklag confined within the thickness of the tube support plates. These criteria are applicable for the sieventh operating cycle caly. At tube support plate intersections, the repair limit is based en malataining steam generater tube serviceability as I

described below

, 4. Degradation attributed to outside diameter strose i '

cerrosies cracking withis the.beunda ei the tube support plate with bobbia voltage less than er equal to 2.0 volts will be allowed te renais in service.

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b. Degradatica attributed to outside diameter stress corrosita cracking within the beunes of the tube support plate with a bobbia voltage greater than 2.0 volts will. be repaired or plegged essept as noted is 4.4.6.4.a.14.s below.

TARI.EY-UNIT 2 3/4 4 12b i

MGNDMENT Iso. 10$'

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A Insert A 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 f rom the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.

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. MacT04 COOLANT $YSTN SA$t$ .

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a. Mechanical i 1. Indications of degradation in the entire length of the sleeve 1 l pust be evaluated against the sleeve plugging limit. l 4

i i 2. . Indication of tube degradation of any type including a i

complete guillotine break. In the tube between ths bottoa of the  !

3 upper joint and the top of the lower roll expansion does not require that the tube be removed free service. .

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3. The tube plugging limit continues to apply to the partion of the tube in the entire upper joint region and in the lower roll  ;

expansion. As noted above, the sleeve plugging Itait applies 1 to these areas also, i 4. The tube plugging limit continues to apply to that portion of

, the tube above the top of the upper joint.

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l b. Laser Welded .

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1. Indications of degradation in the length of the sleeve between

, the weld joints must be evaluated against the sleeve pinging limit. * ,

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2. Indication of tube degradation of any type including a _'

i 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. -

l 3. At the weld joint, degradation must be evaluated in both the l l sleeve and tube. l

4. In a joint with more than one weld, the weld closest to the end 4 . 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 up'ser veld joint and below the lower weld joint.

l F' tubes do not have to be plugged or repaired provided the receinder of the i tube within the tubesheet tiat is above the F* distance is not degraded. The F*

i distance is equal tofL78 !=h:: and is asaaured down from the top of the l

f tubesheet or the bettes of the roll transition, uhtchever is lower in elevation.

!  !=1 d in tht+-44: tree !: = :11r= cf crH-teh for O =7c;..

01:vatt: = = ur: at = =rt:i::ty.

j fteam pnerator tube inspections of operating plants have demonstrated the capabi' ity te reliably detect wastage type degradation that has penetrated 205 of the original tube wall thickness. j l

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' l FAAl.EY-UNIT I 83/4 4-3a AMDOtENT N0. 94 i .--

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t.s4 hek.s pLs al6 a.nc e. 6 r edy curre ni ocedady '

eneasure a &

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