ML20133G580

Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage

ML20133G580
Person / Time
Site:	Farley
Issue date:	01/10/1997
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML19310E989	List: ML20133G466 ML20133G504 ML20133G561 ML20133G580 ML20133G590 ML20133G601
References
NUDOCS 9701160090
Download: ML20133G580 (30)

Text

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Enclosure 4 Revised Technical Specification Pages I

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I 9701160090 970110 PDR ADOCK 05000348 P PDR l

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PEACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continusdl 4.4.6.4 Acceptance Criteria

a. As used in this Specificatien:

1. Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications.

Eddy-current testing indications below 20% of the nominal wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

3. Degraded Tube means a tube, including the sleeve if the tube has been repaired, that contains -

imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.

4.  % Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube or sleeve containing a defect is defective.

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. 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 j7 /fq been sleeved with a welded joint slee.ve, through wall penetration greater than or equal toMof sleeve

/

d 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 4.4.6.4.a.ll 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 less-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.6.3.c, above.  ;

FARLEY-UNIT 1 3/4 4-12 AMENDMENT NO.

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

REACTOR COOLANT SYSTEM i l

SURVEILLANCE REQUIREMENTS (Continued) m _ _ -----_--._-_ ----.__-._-__.-_-.____- - --- - -

8. Tube Inspection means an inspection of the steam generator tube frem the point of entry (het leg side) cempletely around the U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspecticn should include the sleeved portion of the tube.

Tube Repair refers to mechanical sleeving, as WcAP-/J086 && #

h described by Westinghouse report WCAP-11178, Rev. 1, i or lasgr welded sleeving, as described by Westinghouse Mrj WQj O-/@gQ j report r _ _ . _ , which is used to maintain a tube in

' ' " _ji service or return a tube to service. This includes

-s ' __2 --

the removal of plugs that were installed as a corrective or preventive measure.

10. Preservice Inspection raeans an inspection of the full length of each tube ir each steam generator performed by eddy current techniques prior to service to establish a baselle.e condition of the tubing. This inspection shall be performed af ter the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

11. Tube Support Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersecticns, the repair limit is based on maintaining steam generator tube serviceability as described below:

a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosien cracking within the bounds of the tube support plate with bobbin voltage 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 .11. c below.

FARLEY-UNIT 1 3/4 4-12a AMENDMENT NO.

PEACTOR COOLANT SYSTEM BASES 1

The voltage structural limit is the voltage from the burst pressure /bebbin voltage correlation, at the 95-percent prediction interval curve reduced to account for the lower 95/95-percent telerance bound for tubing material properties at 650 'F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential flaw growth during an operating interval and to account for NDE uncertainty. The upper voltage repair limit: V.:n , is determined frem the structural voltage limit by applying the following equation:

Vm = vn - Va - Vcc 1

where Va represents the allowance for flaw growth between inspections and Vcc

! represents the allowance for potential sources of error in the measurement of

' the bobbin coil voltage. Further discussion of the assumptions necessary to deterndne the voltage repair limit are discussed in GL 95-05.

The mid-cycle equation in 4.4.6.a.14.d should only be used during unplanned inspections in which eddy current data is acquired for indications at the tube l support plates.

i 4.4.6.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on the as-found voltage

- distribution rather than the projected end-of-cycle voltage distribution (refer to GL 95-05 for more information) when it is not practical to complete i these calculations using the projected EOC voltage distributions prior to

[

returning the SGs to service. Note that if leakage and conditional burst 2 probability were calculated using the measured ECC voltage distribution for

' the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided per the GL section 6.b(c) criteria.

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.

Plugging or repair will be required for all tubes with imperfections exceeding If a sleeved tube is found to have

] 40% of the tube nominal wall thickness.

) through wall e etration of greater than or equal to 31% for the mechanical j[l k6 ) sleeve and- 7% or the laser welded sleeve of 37+ eeve ts nominal wall thickness in are derived from R.G.

/ the sleeve, 1 must be plugged. The 314 a 1.121 calculations with 20+ added for conservatism. The portion of the tube and the sleeve for which indications of wall degradation must be evaluated :an be summarized as follows:

B 3/4 4-3a AMENDMENT NO.

FARLEY-UNIT 1

._.. ._ . _ _ _ . _ _ ~ _ _ _ _ __ _ . _ _._-__ ..___.. _ _ ___

rrgms ex-ma ggis 3/4 4.6 Lzurruss castertsas aos ottantzau .

3.4.6 nach steen geneseter shall be organsIA.

• 1

! APPLIchBILITY: DWWEB 1, 2, 3 and 4.

M with e.e ., men see ,sessatus r: 2-M- t. = the i e ,arel.

i generater(a) to ofERARIA states psies to imernasing tevT aheve 200*F.

m svavsrt.tm cs =-_ 2 .-

4.4.6.0 Bad steen gameseter shall be demonstseted OPERABLE by parte =meses of the is11entag augmented lasezwies inspostaan psegram and the 1 .a . n e - 4... y . . - _ . . . . . . .

l '.i',el.a

, sm6.e .m.a. e.d.or ., -t.s. .p.emed iaeie::::,':::-

= . .t 1.a.t '

! Table 4.4-1.

• T-- __-8= - ne 4.4.6.2.1 Stees =^w Tsee Sammle *a "'-

eseen generator tehe ena& man aseple eise * . ^5 - seseit ='---ienestism, and the eersespeeding esties segeised sha11 he as speemed in table 4.4-3.

The insesvies 8--. - ~- es steen seensster tehes shall he pereemmed at the i

l "-- speettied is sp s en ==*i- 4.4.5.3 and me 4 ==y==*=d teme fr-shall be vesitied aeseptable per the assuytease esitesia of speettisettes

4.4.6.4. The tubes selosted for seek inaesvios a ,_-a -= *=se. ahall insiste et Selection l 1 east 34 of the metal mesener of tubes in alt stamm *w desipaties. mes i et tubes to be taspected is set affected by the F* l applyseg the esseptions et 4.4.6.1.1.a thsengh 4.4. . 1.e. previene 4

detects or importeetiens in the area .:;-a a by sleeving are est l esasidered se area regoirias re-laspecties. The tubes selected for these i inspections shall be selected en a raades basis mesept: . .

1 i

Winese esposteese is sistlas plante with similas uptes chemLatry l a.

'f indientes esitioni areas to be '- ;- ^% them attlaast Set of l I

the teos a==r--*=d shall be (sem these esitiem1 asema.

• i J l '

i

b. The first sample of tebes selected for seek immesvies

• g r ' = tesheequent to the preseavies 8 1-- *

• et ensk i

)' steen geneaster shall imelades

1. All. eseplegged tehes that psevissely had ^ -- - - *= emal

-- 7 -** - gaestes than 296. l 1

i 8 When refersing to a steen geoeseter tads , the sleeve shall pe asesidamed a past et the tote if the tehe has hees sepaimed per Wessies

. 4.4.6.r.a.F.

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e i.* c ,it. ,ia i. ,u e m i. t. e ,cie u e.1 ,.j 1

h FAAIZY-WTT 2 3/a 4-e < m so. 110

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

f syntytILIA10Ct RE0utasserTS *teentinue]d .

catee*ry inseecties moeults C-1 Less than St of the total tees Laspected are degraded tubes and meme of the inssected tubes are defective.

C-2 One er more tees, but set mars than 14 of the total tubes laspected are defective, or between St and 104 of the total tubes insmeeted are deereded tubes.

c-3 More than 10% of the total tubes inspected are degraded

• -"a er more than it of the insaseted tubes are defective.

4

• Note: In all Laspectiens, previously degraded tubes er sleeves mast eahibit

! significant (greater than 104) further wall penetrations to be included la the aheve perenatage calculations.

i 4. 4. 6. . , .tean .eae,aor , d ta.neetion - za a.d m es to

• I saisianas sample size as detonaimed by specificaties 4.4.5.2.1, all

' -- ' tuses will De taspected withis h-tubanheet -seg6 ear -The-results-of taas.. _

j inspecties will not he e cause for additiemal inspections per Table 4.4-2. l j

l 4.4.6.3 Inspostian Frequeestes, - The above receired inservies

}

inspections of steam generator teos shall be perfesand at the followiat j frequencies i

j a. The first inservice inspecties shall he performed after 6 i

Sffectiva Full Power IIsotha best tatthia 24 ealandar months of i

initial arittenlity. Secoquent inservice taspections shall be perfesand at intervals of met Laos than 12 aos more than 24 l calendar months after the previous laspecties. If two 1

j eenseestave inspections following seavies under Av? eseditions, not including the preservies 4- ;:-T es, result la all i l

inspectica results **WM into the C-1 category er if tus l consecutive inspections demonstrata that previously sheerved i degradaties has met eastissed and as additiemal degradaties has ecourced, the inspecties interval any be antanded to a -i-l of once per 40 months. .

h. If the results of the laservies inspestles of a steam generator coeducted in accordence with Table 4.4-2 at 40 meath intervals f

fall in Category c-3, the inspection iregeeney shall be

! increased te at least ease per 20 anoths. The issrease in inrien frageeney shall syply intil the sesegesat

! ir-;riens satisfy the criteria of Specifie9 tion 4.4.6.3.as the interval any them he entended to a assisnes of emee per de meaths.

c. Additiemal, unsebeduled inservice 1ee; M- shall be f perfassed en each steen generator la aseesdames dth the first I

sample inspecties :;r* **d is Table 4.4-2 durias the shutdoem f

subsequent to any of the fellowing esaditions:

M l j ( te L criteria is applicable te cycle 11 onlyp I 3/4 4-11 merisert 301l0 rARLrr-ver? 2 '

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I

agacTOR C001Alff SYSTEN ..

SURVEILIANCE REQUIREMENTS (Cantinued)

! 6. ~ Plueeine or peosir Limit me:rs the igerfectica depth at er

beyond which the tune shall be repaired (i.e., sleeved) or removed from servios by plugging and is greater than er i equal to 40% of the nominal tube unl1 thickness.

l definition does not apply for tubes that meet the /L* ,

i criteria. For a tube that has been sleeved with a

! mechanical joint sleeve, through wall penetration af greater

! than or equal to 31% of sleeve namtmal wall thickness in the sleeve requires the tube to be removed from service by l plugging. For a tube that has been sleeved with a welded l b oint sleeve, through wall penetration greater than er equal j to 4W6f sleeve nominal wall thickness in the sleeve

! between the weld joints requires the tube to be removed from 1

service by plugging. This definition does met apply to tube j support plate intersections for which the voltage-basee

{

repair criteria are being applied. Refer to 4.4.6.4.a.16 l

for the repair limit applicable to these intersections. For j

a tube with an imperfection er flaw la the tubesheet below 1 the lower jeLat of an installed elevated laser welded i sleeve, no repair er plugging is required provided the

} installed sleeve meets all sleeved tube inspecties

} requirements.

7. Unserviceable describes the condition of a tube er sleeve if f

it laaks 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 11ae or' i feedwater line break as specified la 4.4.6.3.c, above. r 1

8.

• Tube Inspection means an inspection of the steam generater tube from the point of entry (het leg side) completely around the U-bend to the top support af the cold lef. For a j

tube with a tube sheet sleeve installed, the point of entry j

is the bottaa of the tube sheet sleeve below the lower sleeve joint. For a tube that has been repaired by j

sleeving, the tube inspection should include the sleeved 1

porties of the tube.

j S. . Tght .pspau refers to mechasiant sleeving, as described by Wes*t=?mse report scAF-11178, mer.1, or 1sper welded n,- C

g/@f. /30$3; ~ sleeving as described by Westinghouse reperti Z M a e l*

3Q&  :. 4...J .1 = :- *, L L.. ;.a i ,.. 23, li;;, "a.

^

_ -. O, i;;;, ..

1.-...

l WCAP M/N which is used to main'ala a tube la service or retura a tube to service. This includes the removal of plugs that were installed as a corrective er preventive measure.

L f

i [ 99 L* Criteria is appiacehle to cyslo 11 only.

1 l

fit The elevatrA tube sheet sleeve is ausberised for installation j

ealy during the Unit 2 Eleventh Defueling outage.

3/4 4-12a AMDIDMENT No.117 ,

j FARLF.Y-UNIT 2 i @ ,94,Iv6; dvf (d 1

l .- .

, arACTom cooIMF SYSTD8 sav 22.Lanca =-tamarrs ccessinueds l

, - 10. preservice lassestica means an inspectism of the full length of each tee is each steam ganarecer pertesmed by addy cassent teemiques prior to sesvise1be establieb a baseline esadities of the teing. This inspecties shall he performed after the field hydrostatic test sad prior to initial DONER ofuma2'Im using the equiponat and techniques espected

^4 eas.

to he aped daring sehsequent incarvios i-

11. F* Distamos is the distanee of the 7 ' f perties of a tube which provides a suffisiest lenge of undegraded tube atamates to resist pullest of the tube from the tubasheet. The P dLatanes is egual to 1.54 inches plus allowamoe for eddy earrest assert 41 sty measurement and is measured deem from the tap of the tube sheet er she bottaa of the roll tsaasitiaN tahieheves is teuer in elevaties. The allowenee ter  ;

eddy castrust uneestaiaty is desummated in the steen generates addy current inspectica procedure.

12. P Tube is a tee: l a) with depredation equal to er greater than det below the P distpos, and bl whiek has se ladiention of * ; z'riens grestar than er equal to 204 of ameimal unil thiekness taithis the F* distanes, and el that remains inservice.

If the above esitaria esamet he met, them the L* tee criteria may be applied or the tee saast he plupped er sepsised.

13. L' Lemethu is the length of the empended porties of the tube into the tube shoot frem the bottom of the solaed transities er the top of the tube sheet, adhich awar is lever, that has been decantand to be 145 l inches.

I I

14. L Tube : al is a tee with degradatism egeni er granter than 404 below the L* 1ength and not degraded within the L* 1engths b) the eddy l current indicatica of degradaties below the Le length anst be det==4 ==d te he the result of erecks uLth as orientaties ao greater than 15 degrees frem asials el the La ssitaria shall be limited to a maaissan of 600 cube ends per steam generatas; da tehes qualifying as P tebes ase ,

met class 11&ed as L* tubes el a alaiasm of 311ames of age see imee the tubeaheet game the tag of tubenheet er betten of the- se11ed transities, eie ever le loses, shall be *- ; r f using sotattag panoake sail edW eassent teegsigne er am *- ; M:== anthed shoes to give equisalent er better <=8===**= en to ad=*=*4= end length of l antal essakes il a minianen appsegate of 1.57 imekee of eeund asil espansions 31 a ===a- casek length of .39 inchess h) a maniaan of 5 distimet indiestiene with a stag 1e head et huhe dessadations and 13 that remains in servies. .

te Le criteria is applicable to cycle 11 saly. s-r p

mmLst-uurr a 3/4 4-12h Jeemanese no. 116 i

(pq --- p f 3 N 4 ~ 0

/6 uto

g-- _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _

sUptVEILLANCE REQU1ISEENTS (C:ntizued) i /J)# Tube Ess nsin is that portion cf a tube which has been f increased in diameter by a rolling process such that no crevice exists between the outside dienster of the tube and the hole in the tubesheet. Tube espansion aise refers to

that portion of a sleeve which has been incressed in

) diameter by a rolling process such that no crevice exists i

! between the outside diameter of the sleeve and the parent steam generator tube.  ;

// Tube Support Piste sepair IJ.mit is used for the disposition l

et sa alley 600 steen genosator 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 4 intersections, the repair limit is based on maintaining i

steam generator tube serviceability as described below:

i

a. Steam generator tubes, whose degradation is . attributed

~

to outside diameter stress corrosion cracking within i

the bounds of the tube support plate with bobbia j voltages less than or equal to the lower voltage i repair limit (2.0 volts), will be allowed to remain in i service.

f b. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbia voirage greater than the lower voltage repair limit (2.0 volts), will be aired er plugged emeept as noted in 4.4.4.4.a below. ,

! /

, c. Steam generator tubes, with indications of potential degradation attributed to outs &de diameter stress

' corrosion cracking within the bounds of the tubs support plate with a bobbin voltage greater than the l lower voltage repair limit (2.0 volts) but less than i

or equal to the upper voltage repair limit *, may remain in service if a rotating prebe inspection does

' not detect degradation. Steam generator tubes, with

- indications of outside diameter stress corrosion i cracking degradation with a behbia voltage greater

' than the upper voltage repair limit *, will be pimpged

' er repalted.

l 2

}

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• The uppec voltage repair limit is calculated according to the methodology la Generie Letter 95-09 as supplemented.

i i I 3/4 4-13 AhEN!DIENT Wo.117

] TAN.EY-UNIT 2

^

@i bh (c'fy toh y l(0) W

l i REACTOR C001AllT SYSTDI

{, supvtILIANCE REQUIRDEDITS (Continuedi -

i .. . _ _ . - . . _ . _ _ _ , .- . - . .

~

. ._ d. .. If as unschedded add-cycid inspecties is pe.-formed, '

.{~~.?~'Z -the follouias mid; cycle repair limits ly instead of ,

the limits i tified la 4.4.6.4.a. .a. '

! 4.4.4.4.a. . , and 4.4.6.4.41.&#!T The mid-cycle j i

l 11mits arTdetermanos tres the following l equations  !

\

-- \

i v.

3 i

V m. 1.0 + NDE + GrC1.[ h )

i l Vsm"Vsem-!Vam-Val i

Ih)

CL i

. dere:

1 i Vem = upper weltage repair limit i Vm = lower weltage repair limit -

Ves i

= mid-cycle upper weltage repair limit based es tian into cycle 1

! = mid-cycle lower voltage repair limit based Vem en Vaan and time into cycle at = length of time siaee last schedded Laspection dering each Vm and Vm were Laplemented CL = cycle length (the time between two l schedeled et u generator inspections)

Va = structural limit voltage 1

Gr = average growth rate per sysle length

! NDS = 95-pareest, cumulative probability 1

allouence for acadestructive amanisation

! uncertainty (i.e., a value of 20-percent

{ bas been approved by NRC)

{ 1aplementaties of these mid-cycle repair limi bould

! follow the approach as in .4.6.4.a ,

4.4.6.4.s , and 4.4.6.4.a. . /

$ /

) b. The steen generater shall be detemmined om aftas asupleting i the correspeeding actions (plug er repais ef all tubes as::"4==

the plugging er repair limitt required by Table 4.4-2.

3 I

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j ranz.nzramL L 2A4.eman- maimuurus. 115 f L{.(pf, Y j )

i j p --o assfl1 f 3N 4$

4 4

. _ . . . ._..._ _m - _ _._. . . _ . _ _ . __ _ . . _ _

, 1 REACTOR COOLANT SYSTDI I sVWVEILIAleCE REQU!REMENTS (CantinuedI 4.4.6.5 Reports

s. Following each inservice inspection of steam genera o t bes, the number of tubes plugged, repaired er designated / ' .. a each i steam generator shall be reported to the Commission within 15 days

, of the completion of the inspection, plugging or repair effort, b -

4

b. The complete results of the steam generator tube and sleeve inservice inspection shall be suhaitted to the Comunission in a

{ Special Report pursuant to specification 6.9.2 within 12 months

{ following the completion of the inspection. This special Report

shall include

1

1. Number and extent of tubes and sleeves irapected.

2. Location and percent of wall-thickness penetration for each 4

indication of an impetfect.on.

3. Identification of tubes plugged or repaired. .

1 i

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 10CFRSO.13 prior to resumption of plant operation. The written report shall provide a desertptaon of investigations conducted to determine the cause of the tube i degradation and corrective measures taken to prevent recurrence.

d. For implementation of the voltage-based repair criteria to tube 5

support plate intersections, notify the staff prior to returning j the steam generator to service (Mode 41 should any of the

following conditions arise

] 1. If estimated leakage based on the projected end-of-cycle (or i if not practical, using the actual measured end-of-cycle) i voltage distribution exceeds the leak limit (determined fron l the licensing basis dese calculation for the postulated main 4 steam line breaki for the next operating cycle.

I 2. If circumferential crack-like indications are detected at l the tube support plate intersections.

1

,' 3. If indications are identified that extend beyond the confines of the tube support plate.

I 4. If indications are identified at the tube support plate elevations that are attributable to primerg unter stress

{ corregion cracking.

j 1

5. If thi calculated conditional busst probability based on the i projected end-of-eycle ter if not practical, using the

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

] 1 a 10~ , notify the NRC and provide an assessment of the safety significance of the occurrence.

SS L* Criteria is applicable to Cycle 11 only.

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• FARLEY-taf!T 2 3/4 4-13b AMEum ert 30. 115 l l,

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4 4

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s l REACTOR C001 ANT SYSTEM masts 3/4.4.6 STEAM GENERA 20RS The Surveillance Requirements for inspection of the steam generator tubes I ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is i based on a modification of Regulatory Guide 1.03, Revision 1. Inservice j inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design,  !

manufacturing errors, or inservice conditions that lead to corrosion. l Inservice inspection of steen generator tubing also provides a means of characterising the nature and cause of any tube degradation so that corrective measures can be taken.

The pl:at is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may i

likely result in stress corrosion cracking. The eatent of cracking during l plant operation would be limited by the limitaties of steam generator tube l l 1eakage between the primary coolant system and the secondary coolant system l (primary-to-secondary leakage = 150 gallons per day per steen generater) .

Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margia of safety to withstand the leads l l igesed during normal operation and by postulated accidents. Operational leakage of this magnitude can be readily detected by existing Farley Unit 2 radiation monitors. Imakage in excess of this limit will require plaat shutdown and an unscheduled inspection, during totich the leaking tubes will be located and plugged or repaired.

/

The voltage Wased repair limits of 4.4.6.4.a. implement the guidance in GL l 95-05 and are applicable only to Westinghouse-designed steam generators (SGal with outside diameter stress corrosion cracking (ODSCC) located at the tube-to *.ube support plate intersections. The voltage-based repair limits are not applicable to other forms of SG tube degradation nor are they applicable to oDSCC that occurs at other locations within the SG. Additionally, the repair criteria apply only to indications where the detsadation mechanism is dominantly axial ODSCC with no significant cracks esteading outside the thickness of the support plate. Refer to GL 95-05 for additional description of the degradation morphology. I implementation of 4.4.6.4.a requires a derivaties of the voltage structural limit frem the burst versus voltage empirical correlation and them the subsequent derivation of the voltage repair limit from the assuctusal limit (which is then implemmated by this surveillance).

ramucr-ust? 1 a 1/4 4-s meanarr me.115 Q 9,lo3, 3-9, M s %,I&

i 4

REACTOR C001 ANT SYSTDI i

EASES j The voltage structural limit is the voltage from the burst pressure / bobbin j voltage correlation, at the 95-percent prediction interval curve reduced to account for the lower 95/95-percent tolerance bound for tubing material l

properties at 650 'r (i.e., the 95-percent LTL curvel. The voltage structural l

limit must be adjusted downward to account for potential flaw growth during an j operating interval and to account for NDE uncertainty. The upper voltage j repair limitJ Vm, is determine,d from the structural voltage limit by applying the following equations

), Vm = Vss - Vu - Veas where Vu represents the allowance for flaw growth between inspections and v m l represents the allowance for potential sources of error in the measurement of l

the bobbin coil voltage. Further discussion of the assungtions necessary to determine the voltage repair limit er discussed in GL 95-05.

1

! The mid-cycle equation in 4.4.6.4.a. should only be used during unplanned inspections in which eddy current data is acquired for indications at the tube '

} support plates. l f 4.4.4.5 implements several reporting requirements recommended by GL 95-05 for  ;

situations which the NHC wants to be notified prior to returning the SGs to l I service. For the purposes of this reporting requirement, leakage and I conditional burst probability can be calculated based on the as-found voltage j

distribution rather than the projected end-of-cycle voltage distribution j trefer to GL 95-05 for more informatieel when it is not practical to complete l these calculations using the projected ECC voltage distributions prior to l

d returning the SGs to service. Note that if leakage and conditional burst f propability were calculated using the measured EOC voltage distribution for j the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected 20C voltage distribution should be provided l

per the GL section 6.b te) criteria.

l t

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steen generator tube examinations.

l Plugging or repair will be required for all tubes with imperfections exceeding 40% of the tube nominal well thickness. If a sleeved tube is found to have

pf, throu,h .trati .f great.

saan .: egual to sit for the mechanical sleeve 374 for the laser welded sleeve of nantami wall thickness in j

the sleeve uust be plugged. The 314 limits are derived trea R. G.

1.121 calcuAauons with 20% aanes ser conserve am. The portion of the tube i

and the sleeve for which indications of well degradaties must be evaluated can

', be su m cised as follows:

a. Mechanical

1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a couplete guillotine break in the tube between the bottom of the upper joint

' and the top of the lower roll espansion does not require that the l

tube be removed free service.

I FARLgr-UNIT 2 3 3/4 4-3a NENIDENT E3- 115 I b%of 19, Hy W yIt0 j

4 4

J t

_ . . _ . . _ , ._ __ _..._ ~ _...___.__ _ _ . . _ _ _ _ _ _ . _ . . _ . . . . _ _ _ _ _ . _ _ . . _ _ . _ . _ _ _ _ . . . _ _ _ _ _ _ . _ _ . _ _ . . _ _ . . _ .

P=Jctos cootJurr systEN rases I

3. The tube pluggiat limit continues to apply ta th2 porties of the

! tube in the entire upper joint regies and la the 1ewar roll

' empassies. As seted 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.J.he upper 3eint.

a i

m. Laser Welded 1

Indications of degradation in the length of the sleeve between W i

wold joints saast be evaluated against the sleevs plugging limit.

2. Indication of tube degradaties of any type including a oesplete break in the tube between the upper tsaid joint and the lower weld joint does set require that the tube he renewed irea service.

3. At the wald joint, degradetaan enast be evaluated in both the l

sleeve and tube. ,

i

4. In a joint trith more than see wald, the weld closest to the eed of the sleeve represents the joint to be inspected and the limit of the sleeve inspecties, i

5. The tube plugging limit oesta === to apply to the portion of the tihe above the upper wald joint and below the lower wald joint.

of the I r* tubes de set have to be plugged or repaired provided the . ---a a-. The tube within the tubesheet that is above the F* distanes is met degraded.

r* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is asasured denen from the top of the tubesheet er the betten of the roll transities, whichever is lower la alevation.

• 1a similar to F*s however, bands of axial degradaties are allowed as long '

as sufficient asa-degraded tubing is available to ensure structural and 1eakage iategrity. L* criteries is only applicable for Unit 2 Cycia 11.

l Provided below is the Unit 2 Cycle 11 opecific L* criteries:

i 1

1 i

l a 3/4 4-m Annutsam so.116 rant.sy-avir 2 -

@3;Tfll0,l'5 y

1 I

I

_. . _ _ _. _ _ ..m . . . ~ . . - _ .. __ . _ . . . _ . _ . . _ _ _ _ _ . . _ _ . _ _ . _ _ .. _ ._._ _. ___ _ . ._._ _ -,

s f

RIACTOR f WWWrf SYSTDI I 1 BASES 1

Unit 2 Cycle 11 Specific L' Cr.iteries l

! Parameter Value }y ,

Minimum distance of SRE 2.01 inches l j Maximum number of distinct degradation areas in a 5

band i

Maximum inclination angle within a single band 15 degrees Maximum crack length .39 inches j j j

Minimum distance of SRE from the bottom of the 1.45 inches transition roll to the top of the indication 1 l steam generater tube inspections of operating 11 ants have demonstrated the

, capability to reliably setect wastage type eegradation that has penetrated 20+

of the original tube us11 thickness.

i whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported t: the Commission pursuant ,

I to 10 CFR S0.73 prior to resumption of plant aparation. Such cases will be 3 considered by the Commission en a case-by-case basis and any result in a i j requirement for analysis, laboratory esaminations, tests, additional eddy-current inspecties, and revisies to the Technical Specifications, if necessary.

8 i

1 1

l 1

1 4

4 i

l i

, i 1

d i j Faamm-4astr 2. a 3/4 4 se asenresarr me. 115 l i

4 a

l l

l Unit 1 Technical Specification Pages Replacement Pages Page 3/4 4-12 Replace Page 3/4 4-12a Replace Page B 3/4 4-3a Replace 4

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

1 l

l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 Acceptance Criteria l

a. As used in this Specification:

l 1. Imperfection means an exception to the dimensions, finish l

or contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall l thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.

3. Degraded Tube means a tube, including the sleeve if the tube has been repaired, that contains imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.

4.  % Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube or sleeve containing a defect is defective.

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 nondnal tube wall thickness. 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 slar.w requires the tube to be removed from service by plugging. For a tube that has been sleeved +lth a welded joint sleeve, through wall penetr;rion greater than or equal to 24% of sleeve l 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 4.4.6.4.a.11 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.

EARLEY-UNIT 1 3/4 4-12 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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 reports WCAP-13088, Revision 4, and WCAP-14740, which is used to l 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.

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. Tube Support Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair limit is based on naintaining steam generator tube serviceability as described below: )

i

a. Steam generator tubes, whose degradation is )

attributed to outside diameter stress corrosion j cracking within the bounds of the tube support plate with bobbin voltage 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.11.c below.

EARLEY-UNIT 1 3/4 4-12a AMENDMENT NO.

l l

[ REACTOR COOLANT SYSTEM 1

BASES The voltage structural limit is the voltage from the burst pressure / bobbin voltage correlation, at the 95-percent prediction interval curve reduced to l account for the lower 95/95-percent tolerance bound for tubing material properties at 650 F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential flaw growth during an operating interval and to account for NDE uncertainty.

The upper voltage repair lindt; Vun, is determined from the structural voltage limit by applying the following equation Vunt " Vst. - Vor - Vug where Vor represents the allowance for flaw growth between inspections and Vnc represents the allowance for potential sources of error in the measurement of the bobbin coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit are discussed in GL 95-05.

The mid-cycle equation in 4.4.6.a.14.d should only be used during unplanned inspections in which eddy current data is acquired for indications at the tube support plates.

4.4.6.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage and conditional burst probability can be calculated based on the as-found voltage distribution rather than the projected end-of-cycle voltage distribution (refer to GL 95-05 for more information) when it is not practical to complete these calculations using the projected EOC voltage distributions prior to returning the SGs to service. Note that if leakage and conditional burst probability were calculated using the esasured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided per the GL section 6.b(c) criteria.

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.

Plugging or repair will be required for all tubes with imperfections  !

exceeding 40% of the tube nominal wall thickness. If a sleeved tube is found to have through wall penetration of greater than

)

or equal to 31% for the mechanical sleeve and 24% for the laser welded l l sleeve of sleeve nominal wall thickness in the sleeve, it must be l l plugged. The 31% and 24% limits are derived from R.G. 1.121 l calculations with 20% added for conservatism. The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can be summarized as follows:

EARLEY-UNIT 1 B 3/4 4-3a AMENDMENT NO.

i l

l l

l Unit 2 Technical Specification P&ges Replacement Pages 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 4-13 Replace Page 3/4 4-13a Replace Page 3/4 4-13b Replace Page B 3/4 4-3 Replace Page B 3/4 4-3a Replace Page B 3/4 4-3b Replace Page B 3/4 4-3c Delete

m __ .. _ _ m_. . _ _ _ _ - _. ___. _ _ __ . . _ _ _ _. . . . _ . . . . _ . ._ _ _. .

I REACTOR COOLANT SYSTEM l

l 3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION l

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 incret. sing 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.

4.4.6.1 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 4.4-1.

4.4.6.2.1 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube ednimum 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* designation. When l applying the exceptions of 4.4.6.2.1.a through 4.4.6.2.1.c, previous l 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 plants 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: I l

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.

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 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 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* Tube Inspection - In addition to the minimum sample size as determined by Specification 4.4.6.2.1, all F* 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 lear;t 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:

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

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 l meet the F* criteria. For a tube that has been sleeved l l 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 24% of sleeve l 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 4.4.6.4.a.16 for '

the repair limit applicable to these intersections. For a tube with an imperfection or flaw in the tubesheet below 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.

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 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 Westinghouse report WCAP-11178, Rev. 1, or laser welded sleeving as described by Westinghouse reports WCAP-13088, Revision 4, and WCAP-14740, 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.

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

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r t

l REACTOR COOLANT Sv7 TEM 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 F ;lER OPERATION using the equipment and techniques expected to be used during subsequent ,

inservice inspections.

I

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 j procedure.

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 Expansion is that portion of a tube which has been l 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 l crevice exists between the outside diameter of the sleeve l and the parent steam generator tube.

14. Tube Support Plate Repair Limit is used for the l disposition of an alloy 600 steam generator tube for continued service that is experiencing predondnately axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair limit is based on maintaining steam generator tube j serviceability as described below:

l l

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

l l

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

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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.14.c below. l

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 remain in service if a  !

rotating probe inspection does not detect degradation. Steam generator tubes, with indications of outside diameter stress corrosion cracking degradation with a bobbin voltage greater than the upper voltage repair limit *, will be plugged or repaired.

d. If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in i 4.4.6.4.a.14.a, 4. 4. 6. 4. a .14.b, and 4. 4. 6. 4. a .14. c. l

~

The mid-cycle repair limits are determined from the following equations:

Vst VMunt= 1.0 + NDE + Gr [ CL-At ]

CL V Mtat=Vguat-[Vunt-Vt atl [ CL-At )

CL I

J l

\

l l

l The upper voltage repair .imit is calculated according to the methodology in Generic Letter 95-05 as supplemented.

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

._, _ . _ _ , _ _ _ _ _ _ _ _ _ ._ .- _ . _ _ __. ._ . _ _ . _m 1

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4 where

=

Vuu upper voltaqe repair limit I v ue = lower voltage repair limit ,

= mid-cycle upper voltage repair limit based on Vamt i time into cycle i Van = mid-cycle lower voltage repair limit based on i Vmmt and time into cycle g At = length of time since last scheduled  ;

l inspection during which Vun and von were implemented CL = cycle length (the time between two scheduled steam generator inspections)

Yn = structural limit voltage ,

Gr = average growth rate per cycle length  !

NDE = 95-percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20-percent has been 7 l approved by NRC) ,

! Implementation of these mid-cycle repair lindts should follow the same approach as in TS 4.4.6.4.a.14.a, 4.4.6.4.a.14.b, and 4.4.6.4.a.14.c.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair of all  !

tubes exceeding the plugging or repair limit) required by Table '

4.4-2. ,

4.4.6.5 Reports

a. Following each inservice inspection of steam generator tubes, i the number of tubes plugged, repaired or designated F* in each l [

steam generator shall be reported to the Commission within 15 days of the completion of the inspection, plugging or repair effort. i

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 following the completion of the inspection. This Special Report 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. j

3. Identification of tubes plugged or repaired.

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

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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

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 intersections.

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

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

REACTOR COOLANT SYSTEM BASES 3/4.4.6 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 150 gallons per day per steam generator). Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operational leakage of this magnitude can be readily detected by existing Farley Unit 2 radiation monitors. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired.

The voltage-based repair limits of 4.4.6.4.a.14 implement the guidance in l GL 95-05 and are applicable only to Westinghouse-designed steam generators (SGs) with outside diameter stress corrosion cracking (ODSCC) located at the tube-to-tube support plate intersections. The voltage-based repair limits are not applicable to other forms of SG tube degradation nor are they applicable to ODSCC that occurs at other locations within the SG.

Additionally, the repair criteria apply only to indications where the degradation mechanism is dominantly axial ODSCC with no significant cracks extending outside the thickness of the support plate. Refer to GL 95-05 for additional description of the degradation morphology.

I Implementation of 4.4.6.4.a.14 requires a derivation of the voltage structural limit from the burst versus voltage empirical correlation and then the subsequent derivation of the voltage repair limit from the structural limit (which is then implemented by this surveillance).

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

l l

REACTOR COOLANT SYSTEM BASES The voltage structural limit ja the voltage from the burst pressure / bobbin voltage correlation, at the 95-percent prediction interval curve reduced to account for the lower 95/95-percent tolerance bound for tubing naterial properties at 650 F (i.e., the 95-percent LTL curve). The voltage structural limit must be adjusted downward to account for potential flaw growth during an operating interval and to account for NDE uncertainty.

The upper voltage repair limits Vunt, is determined from the structural voltage limit by applying the following equation:

Voax, = V,u, - Va, - Vux  ;

where Vc, represents the allowance for flaw growth between inspections and Vuu represents the allowance for potential sources of error in the measurement of the bobbin coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit are discussed in GL 95-05. ,

The mid-cycle equation in 4.4.6.4.a.14.d should only be used during l unplanned inspections in which eddy current data is acquired for ,

indications at the tube support plates. l l

4.4.6.5 implements several reporting requirements recommended by GL 95-05 for situations which the NRC wants to be notified prior to returning the SGs to service. For the purposes of this reporting requirement, leakage l and conditional burst probability can be calculated based on the as-found  ;

voltage distribution rather than the projected end-of-cycle voltage  !

distribution (refer to GL 95-05 for more information) when it is not practical to complete these calculations using the projected EOC voltage distributions prior to returning the SGs to service. Note that if leakage and conditional burst probability were calculated using the measured EOC voltage distribution for the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting criteria, then the results of the projected EOC voltage distribution should be provided per the GL section 6.b(c) criteria.  ;

l Wastage-type defects are unlikely witn proper chemistry treatment of the l secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.

Plugging or repair will be required for all tubes with imperfections exceeding 40% of the tube nominal wall thickness. If a sleeved tube is found to have through wall penetration of greater than or equal to 31% for the mechanical sleeve and 24% for the laser welded sleeve of sleeve nominal wall thickness in the sleeve, it must be plugged. The 31h and 24% limits are derived from R. G. 1.121 calculations with 20% added for conservatism.

The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can be sunnarized as follows:

a. Mechanical

1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.

EARLEY-UNIT 2 B 3/4 4-3a AMENDMENT NO.

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' REACTOR COOLANT SYSTEM BASES

2. Indication of tube degradation of any type including a complete guillotine break in the tube between the bottom of the upper joint and the top of the lower roll expansion does not require that the tube be removed from service.

l 3. The tube plugging limit continues to apply to the portion of l

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.

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

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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 i the tube above the upper weld joint and below the lower weld joint. l 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.

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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 fer analysis, laboratory examinations, tests, additional eddy-current inspectio . ~nd revision to the Technical Specifications, if necessary. l l

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

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