ML20134G960

Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process

ML20134G960
Person / Time
Site:	Farley
Issue date:	11/11/1996
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML19353D969	List: ML20134G940 ML20134G960 ML20134G973
References
NUDOCS 9611130449
Download: ML20134G960 (5)

Text

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Enclosure 1 Technical Specification Pages I

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i 9611130449 961111 PDR ADOCK 05000364 P PDR

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, REActua COULAfr? SYSTEM i

, s SURVEILLANCE Rf#)tREMzwTS (Continued)

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6.

f Pluesine or Repair Limit means the imperfection depth at or g g beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or

! lAg y M kiGa Dr equal to 40% of the nominal tube wall thickness. This

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j 4 4g Q definition does not apply for tubes that meet the F*/L'u criteria. For a tube that has been sleeved with a

! $ hj'o// MM mechanical joint sleeve, through wall penetration of greater j

i M than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by gh ge j#Fy@EM plugging. For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal 1 Cf / 4 to 37' of al**v* n**dnal **11 thicka**s in the sleeve

{ J4g between the weld joints requires the tube to be removed frem i fg service by plugging. This dettaition does not apply to tube g h Aged /K support plate intersections for which the voltage-based

+ repair criteria are being applied. Refwr to 4.4.6.4.a.16

• fortherepairlimitapplicabletotheseintersections.g

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YM 7. Unsesvionable describes the condities of a tube er sleeve if it leaks or contains a defoot large eneegh to affect its

, structural integrity in the event of an operating Basis i

' Barthquake, a less-of-ooolent accident, or a steen line or '

pyde b feekster line break as specified la 4.4.6.3.c, above.  ;

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. Tube Inspecties means as inspecties of the steam generator tube from the point of entry ~(bot leg side) coupletely jM around the U-bend to the top support of the cold leg.) For a i gM tube that has been repaired by sleeving, the tube inspection dh hM should include the sleeved portioa of the tube. 1 MW .. ,ube .easic refers to --cai steeving, as dese,aed by Westingbouse report WCAP-11178, .ev.1, or laser welded '

sleeving as described by Westinghouse report WCAP-1247 , 1 which is used to malatata a tube in service or retura a tube to service. This includes the removal of plugs that were installed as a corr 3ctive er preventive measure, 4

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00 L* Critaria is applicable to cycle 11 only.

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• l FARLEY-UNIT 2 M e$y LW 3/4 4-12a AMzucMaw? po. I1$

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}. ~ , REACTOR C0014rf SYSTDI j , , SURVEILLANCE REQUIREMENTS (Conti_nued) i 15. Tube Expansion 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 i the hole in the tubesheet. %

16. Tube Support Plate Repair Limit is used for the disposition 1 of an alloy 600 steam generator tube for continued service j that is experiencing predominately axially oriented outside a

diameter stress corrosion cracking confined within the l

thickness of the tube support plates. Attubesupportplatel i intersections, the repair limit is based en maintaining j steam generator tube serviceability as described below:

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a. Steamgeneratortubes,ubosedegradationisattributedl to outside diameter stress cerrosion cracking withis j the bounds of the tube support p1C m with bobbin

' voltages less than or equal to the lower voltape repair limit [2.0 volts), will be allowed to remain la servios.

a l b. Steamgeneratortubes,whosedegradatiesisattributedl to outside diameter stress oorrosies cracking withia l

- the bounds of the tube support plate with a bobbia

! voltage greater than the lower voltage repair limit

[2.g volts), will be repaired or p1opped esospt as j moted in 4.4.6.4.a.16.s below.

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! c. Steam generator tubes, with indications of potential j degradation 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 %imit [2.0 volts] but less than or equal to the uppet voltage repair limit *, may remain in service if a rotating probe inspecties does l

not detect degradation. Steam generator tubes, with l

indications of outside diameter stress corrosion

. cracking degradaties with a bobbia voltage greater

! than the upper voltage repair limit *, will be plugged l or repaired.

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• The upper voltage repair limit is calculated according to the i methodology in eeneric Letter 95-05 as supplemented.

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FARLEY-UNIT 2 3/4 4-13 AMENDMENT No.115 l

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. REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) l

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 i definition does not apply for tubes that meet the F*/L*n i criteria. For a tube that has been sleeved with a l 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 j

plugging. For a tube that has been sleeved with a welded  !

l 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 l support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.6.4.a.16 for the repair lindt applicable to these intersections. For  ;

a tube with an imperfection or flaw in the tubesheet below L l the lower joint of an installed elevated laser welded  ;

sleeve, no repair or plugging is required provided the  !

installed sleeve meets all sleeved tube inspection  ;

requirements.

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7. Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its f

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 with a tube sheet sleeve installed, the point of entry is the bottom of the tube sheet sleeve below the lower sleeve joint. 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 l

(' Westinghouse report WCAP-lll78, Rev. 1, or laser welded i sleeving as described by Westinghouse report WCAP-12672, or, l for elevated sleeves'", Southern Nuclear letters dated l August 23, 1996, November 6, 1996, and November 11, 1996, l

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which is used to maintain a tube in service or return a tube i  !

to service. This includes the removal of plugs that were installed as a corrective or preventive measure, i i

1. 1. L* Criteria is applicable to Cycle 11 only.

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1. 1. 1. The elevated tube sheet sleeve is authorized for installation  ;

only during the Unit 2 Eleventh Refueling outage. l FARLEY-UNIT 2 3/4 4-12a AMENDMENT NO. i

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, REACTOR' COOLANT SYSTEM '

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SURVEILiANCE REQUIREMENTS (Continued)

15. Tube Expansion 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. Tube expansion also refers to '

that portion of a sleeve which has been increased in diameter by a rolling process such that no crevice exists between the outside diameter of the sleeve and the parent '

steam generator tube.

16. Tube Support 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 cracking confined within the l thickness of the tube support plates. At tube support plate '

intersections, the repair limit is based on maintaining steam generator tube serviceability as described below: i

a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion 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.

b. 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.16.c below.

c. Steam generator tubes, with indications of potential degradation 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) but less than  !

or equal to the upper voltage repair limit *, may i remain in service if a rotating probe inspection does not detect degradation. Steam generator tubes, with l

indications of outside diameter stress corrosion '

cracking degradation with a bobbin voltage greater than the upper voltage repair limit *, will be plugged

• or repaired.

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i l l l l l

l l The upper voltage repair limit is calculated according to the  !

methodology in Generic Letter 95-05 as supplemented.  ;

EARLEY-UNIT 2 3/4 4-13 AMENDMENT NO.

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