ML20135C494

Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend

ML20135C494
Person / Time
Site:	Farley
Issue date:	02/24/1997
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20135C482	List: ML20135C479 ML20135C494
References
NUDOCS 9703040074
Download: ML20135C494 (46)

Text

A e

a Enclosure 1

Technical Specification Pages i

9703040074 970224 PDR ADOCK 05000348 PDR P

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REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS 4

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LIMITING CON 0!T10N FOR OPERATION

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3.4.6 Eacn steam generator snall De OPERABLE.

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APPLICA81LITY: MODES 1, 2, 3 and 4 ACTION:

With one or more steam generators inoperable, restore the inoperable generator (s) to OPERA 8LE status prior to increasing Tavg above 200*F.

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SURVEILLANCE REQUIREENTS i

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 Steen Generater Sample Selection and Inspection - Each steen generator shall be determined urtRABLE escing snuteoun Dy se' ecting and inspecting at least the minimum number of steam generators specified in Table 4.41.

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Steam Generator Tube # ample Selection and Inspection - Th steam S

j 4.4.6.2 catt

, and the generator tube m1ntmum sample size, inspection result class corresponding action required shall be as specified in Tab 4-2.

The i

inservice inspection of steam generator tubes shall be performed at the l

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 35 of the i

l total number of tubes in all steam generators. When applying the exceptions of 4.4.6.2.a through 4.4.6.2.c. previous defects or imperfections in the area l

repaired by sleeving are not considered an area requiring reinspection.

The tubes selected for these inspections shall be selected on a randan basis except:

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a. )tiere experience in sis 11ar plants vita similar eter chemistry indicates critical areas to be inspected, then at least 505 of the

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tubes inspected shall be from these critical areas.

l The first sample of tubes selected for each inservice inspection d

i b.

(subsequent to the preservice inspection) of each steam generator shall i

2 include:

b

1. When referring to a steam generator tube, the sleeve shall be considered a part of the tuce if tne tube has been repaired per Specification 4.4.6.4.a.9.

AMNDENT N0. 25, i FARLEY UNIT 1 3/4 4-9

J REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1.

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

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2.

Tubes in those areas where experience has indicated potential problems.

l I.

At least 3% of the total number of sleeved tubes in 3

all three steam generators or all of the sleeved tubes j

in the generator chosen for the inspection program, whichever is less. These inspections will include

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both the tube and_the sleeve.

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A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.

If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

$W Indications left in service as a result of application of the tube support plate voltage-based repair criteria shall be inspected by bobbin coil probe 1

during all future refueli U utages.

-3 c.

The tubes select as t second and third samples (if required by Tabl

.4-2 during each inservice inspection may be subjected to a partial tube inspection provided:

i 1.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2.

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

d.

Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and cold-leg tube support plate

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intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.

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

i FAFLEY-UNIT 1 3/4 4-10 AMENDMENT NO.

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SU;;VE!11ANCE ARQUI ADENTS (Cestinuedi Catoesty Inseestie3 Desults C-1 hoss than St of the total tunes inspected are segrasee tees and none of the inssected teos are defeettwo.

l C-2 One er more tees, but not more than 1% of the total tubes inspected are defective, or between St and let of the totsi j

teos inspected are deersdod tubes.

1 C-3 More than 10% of the total tunes inspectee are degreeed j

tees or more than 14 of the inssected tees are defeettwo.

l Note: In all inspections, previously degrades tubes or sleeves aust i

eahibit significant (greater than tell further well penetrations to be j

imeluded la the above percentage estoulettees.

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4.4.6.3

'I=r

__ia= Frecuencies - The above required inservice inspeettene of steen generator teos shall be performed at the following l

frequencies:

i a.

The first inservios inspectica shall he performed after 6 i

Ef fective mail power Heaths but withia 24 ealander meaths of i

tattial criticality. Seseguest taservice inspections shall he periossed at intervals of not less than 12 eer esse than 24 ealandas months after the previous inspecties. If tus eenseestive inspections following servies under JWf l

eenditions, not imeloding the preservies Laspecties, recent is a&& inspecties resmits falling into the C-1 estegory er i

12 tus====* ave Laepeettees dessestrate that provisuely i

eheerved degradatica has act 'esatinued and me **==a1 i

degredsties has seestred, the.aded a. moi a of -

,.,r==*i-interval gp3 t

ama y be

4..e.es.

b.

If the results of the inservice laspoetion pha a generates seeducted is aseerdanes with Tab 1Pt.4-et 40 meeth intesvals !ali La Category C-3, the inspeetten fregemesy abati he taeressed to at least ease per 20 months.

j The increase is taspection f requency shall apply eM1 the subsegoemt inspections satisfy the criteria of specificaties 4.4.6.3.as the interval any then be estended to a esa of once per 48 anaths.

f.4,,3 c.

Additiemal, umscheduled inservice inspections e be i

perfoamed en each staas generator la aces th the j

first sample inspection specified is Tab

.4-2 enstag the shutdans suboeguent to any of the following conditions:

1.

primary-to-seeendary tube leaks teet tacludtag leets i

originating from tube-to-tube sheet melds) La eseems of the limits of specifiesties 3.4.1.2.

3.

A setente occartenes greater than the operating tesis Barthquake.

3.

A less-et-seelaat accident requiring actuation of the engineered safeguards.

4.

A mata steam line er feedwater line break.

rnal,gy-Upt!T 1 3/4 4-11 AMDfDMDIT NO. 44, l 117

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REACTOR COOLANT GYSTEM SURVEILLANCE REQUIREMENTS (Continueo) 4.4.6.4 Acceptance Criteria a.

As used in this Specification:

1.

Imperfection means an exception to the dimensions, j

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 l

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

i 4.

% Degradation means the percentage of the tube or sleeve wall thickness affected or removed by j

degradation.

S.

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 7/

been sleeved with a welded joint sleeve through wall

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penetration greater than or equal to184k'of 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 lindt applicable to these intersections.

7 Unserviceable describes the condition of a tube er 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 NC.

REACTOR COOLANT SYSTEM SURVEILLANCE REC'JIREMENTS (Continued) i B.

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.

Tube Repair refers to mechanical sleeving, as WuP- #os#asw ) described by westin9 ouse report wCAP-11178, h

Rev. 1, 3

or lasgr welded sleeving, as described by westinghouse M e) W $../4 M

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report r ___-_, which is used to maintain a tube in

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f service or return a tube to service. This includes

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

j 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 tie equipment and techniques expected to be used during sWasequent 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 maintaining steam generator tube serviceability as described below:

a.

Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion 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 bebbin voltage greater than the lower voltage repair limit [2.0 volts), will be repaired or plugged ex:ept as noted in 4.4.6.4.a.11.c bel w.

EAPLEY-UNIT 1 3/4 4-124 AMENDMENT MO.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continusd) b.

The steam generator shall be determined OPERABLE af ter completing the corresponding actions (plug or repair of all be d

1 ging or repair limit) required by 4.4.6.5 Reports Following each inservice inspection of steam generator a.

i tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the commission within 15 days i

of the completion of the plugging or repali ef fort.

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b.

The complete results of the steam generator tube and sleeve inservice inspection shall be submitted to the Commission in 1

a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This 3

Special Report shall include:

1.

Number and extent of tubes and sleeves inspected.

3 2.

Location and percent of wall-thickness penettation for each indication of an Luperfection.

3.

Identification of tubes plugged or repaired.

c.

Result of steam generator tube inspections which fall into category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 100FR50.73 prior to resumption of plant operation. The v2itten report shall provide a description of investigr.tions conduct ed to determine the cause of the tube degradation and cocrective measures taken 3

to prevent recurrence.

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d.

For implementation of the voltage-based repair criteria to tube support plate intersections, notify the NRC staf f prior to returning the steam generators to service (Mode 4) should any of the following conditions arises f.

1.

If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured 1

end-of-cycle) voltage distribution exceeds the leak i

limit (determined from the lice.nsing 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.

J 3.

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

1 4.

If indications are identified at the tube support plate elevations that are attributable to primary i

water stress corrosion cracking.

l S.

If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, s

using the actual measured end-of-cycle) voltage distribution exceeds 1 x 10**,

notify the NRC and i

provide an assessment of the safety significance of the occurrence.

FARLEY-UNIT 1 3/4 4-13 AMENDMENT NO.

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TABLE 4.4-3 STEAM GENERATOR REPAIRED TUBE INSPECTION IST SAMPLE INSPECTION E

2ND SAMPLE INSPECTION yy Saniple Size Result Actions Required E

Result Action Required Q

A minimum of C-1 None NA NA 20% of h

repaired tubes c4 (1) (2) m C-2 Plv.g or repair defective l

C-1 None repaired tubes and inspect B

100% of the repaired tubes in C-2 Plug or repair defective this steam generator.

repaired tubes.

C-3 Perform action for C-3 I

result of first sample.

C-3 Inspect all repaired tubes in All other steam None this steam generator, plug or generators are repair defective tubes and C-1.

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inspect 20% of the repaired Some steam Perform action for C-2 tubes in each steam generator generators C-2 result of first sample.

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but no additional i

Notification to NRC pursuant steam generators to 10 CFR 50.72 (b) (2).

are C-3.

Inspect all repaired tubes IAdditionalsteam generator is C-3.

in each steam generator and plug or repair defective tubes.

Notification to NRC pursuant to 10 CFR 50.72 (b) (2).

I (1)

Each repair method is considered a separate population for determination of scope expansion.

hg (2)

The inspection of repaired tubes may be performed on tubes from 1 to 3 steam generators based on outage g

plans.

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REACTOR CCOLANT SYSTEM BASES 1

The voltage structural limit is 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 for tubing material properties at 650 'T (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, Vmu, is determined from the structural voltage limit by applying the following equation:

V m = V,6 - v, - Va s

where V., represents the allowance for flaw growth between inspections and Vec 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 is contained in GL 95-05.

The mid-cycle equation in 4.4.6.4.a.ll.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 reconsnended by GL 95-05 for situations in 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 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.

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 throuah wall nenetration of greater than or equal to 31% for the mechanical

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sleeve an 37 or the laser welded sleeve o e ve nominal wall thickness in j[ 7

__ the sleeve, must be plugged. The 31% an 37 limits are derived from R.G.

1.121 calculations witn gut acced 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.

.73-

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3/4.4.6 WTENE N i

L2ptITIss cussarttes fem artist 2W i

3.4.6 ame steen penasstes shall he creas&E.

4 d

AttinEBRELETY:

3E5 5 1, 2, 3 and 4.

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With one os some steen t=====*==

4- ;:W ; seatese the Laeperable geneestes(s) to apuesta statue poies to Sammenstag tagg aheve 200*F.

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4.4.6.e see stems pen seter shnu be demonsteemed erassma tr l

per8====== of the telleming engmented immeswies taspostaan psegsam and the segnasemmets et a=== =** = 4.8.L..

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tes e inspeestag at least to N eh of steen gemeentese speettted is i

Tekle 4.4-1.

t

[=a and the W=T estaan segutand es41 he se

&a SahdiFE.4-t d k'W' e

j The tasasetes aespesasen es sneen gemasems tees he pastemmed et me tsegemoeies mp==8 *'d la pes =**= 4.4.6.3 and me leeposeed teos t

l shall be =.sead esemptable per the assuytease settes&s et spesisteet&am 4.4.6.4. The tehes selected $es seek innesvise 4==y a= ahall instado at j

Senestaan least 34 et the metal asuher of teos is a11 steen et tees to be taspesand to met affected hr the r*

igenties. then l

applying the emeeptions et 4.4.6.2.1.a thseegh 4.4.

1.s, psevious j

defects es asymateettees in the asas sepaized by alessing ase met j

eensidased as ases segeizing so-laspecties. The tobas selected ter these

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inspections shall he selected es a saades basis enesytt i

haze==y-et-La =&s=81=* pleets uith siedlas esp'ter shamistsy l

a.

indientes esitten1 areas te he inspected, them atllamat 584 et the teos *-. r ' shall he isom these esittest amens.

1 h.

The 21 set semple et teos selected for eet ineasvise Aaepeaties (===*= ave to the psenervies * ; ^*=* ed seek stema gamessant shall imeledes 1.

All amaplopped tese thes ;-._1:

• = bad ' '-

~ '- smal i

pesetaattees gamates them 306.

8 When secessias to a steen geasseter tidse, she sleeve shall pe seasidased a past et the take if the tee has been seynised pas spesitieneien j

4.4.6.4.a.f.

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j n v criteste se e,,uemi. to erste il emir.;

mensmer so.110 rm.sr-awzT 2 s/4 4-e hSt k

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i REACT 0ft C001 ANT SYSTEM SUnvt3LLANCE y1REMENTS tcentinued) 1 2.

Tubes in those areas where emperience has indicated potential problems.

b.

At least 3% of the total number of sleeved tubes in all 3

4 three steam generators er all et the sleeved tubes in the Theseinspectionswillincludeboththetubeandthe]I generator chosen for the inspection program, whtchever is i

loss.

sleeve.

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J M A tube Laspecties (pursuant to Specificaties 4.4.6.4.a.8) shall be perteamed en eseh selected tube. If any selected tube does met passit the passeque of the eddy eurrent probe for a tube er sleeve M dem, this shall be recorded and i

an adjacent tube shall be selected and subjected to a tube i

inspection.

Indications left la servies as a resalt of application of j

the tube oggert plate weltage-based repair criteria shall j

be Laspected by hobbia soil probe during all future

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s[ested as the second and thisd semples (if required by l

c.

The tab 4-25 desing ese Lasesviso inspeetama any be subjestad te a partial tube inspecties psevideds i

1.

The tubes selected for these samples include the tubes from these areas of the tube sheet array dere tubes with l

imperfections were previously found.

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2.

The inspections include these portions of the tubes where imperfections were previously found, i

d.

Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbia coil inspection for l

hot-leg and cold-leg tube support plate intersections dem to the lowest cold-leg tube support piste with kasua outside diameter stress corresten cracking (ODSCC) indications. The determination of the lowest eeld-leg tube ogpert plate intersections having l

ODsCC indications shall be based en the pattesmanes of at least a 20 percent randen sampling of tubes inspected over their full length.

i The results of each sample inspection shall be classified into one of the l

te11 ewing three categoriews i

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asemansur so.115 l

ramsay-uutt 1 1/4 4-1, b

0)W)/0h 4

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3EPCND 000MWT 5T9738

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l senvaruAucs yseerfs-(castiauedi.

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g _eeery inseesties assults d

C-1_

tess than St et the total tees laspected ase engraded teos " maae et the t --- ted tubes amo defelve.

C-2 ese er maae tese, but act asse than 16 et the total teos inspected ase dateetive, or hetmeen St and 104 et the total tebes insmeeted are deeredad tebes.

1 C-3 asse than tot of the totd tubes taspected are degraded

-"=' takes are 4E26ctive.

tobes or asse than it of the -

t Notes la all taspeetiens, previously degredad tebes or sleeves mast enhibit j

significant Igseater than let) further wall penetsstions to be imeloemd La ths aheve perenatage salenlations.

4 4.4.6.2.2 Steam Gesameter F*

- la addities to I

miniaan sample size as 2--""

Dy spee121est&es 4.4.6.1.1, all j

........... -. W uLu h

• T W 4 thia the-eensheet @= -The-sesalta

. _ i j

1&pecties uL11 act he a eesse for additiemal laspections per

.4-2 l

M+4 5 j

4.c.6.3 tassee=4em rieewessee. - he abm se,4:ss insenesse tw-M-er steam gemasseer sees shall be paressmed at the foueuses i

i freguessies a.

Se Riset immervice sepa-shd1 he perteamed after 6 l

atteetive Fdi Bouer IIsoths but with&a 24 annendar meaths og initial esittenlity. sesegment inesevies Laspostians shall he l

performed at intervals et met less them 12 mer nose thes 34 i

j calendar anoths after the previous insposion. If tuo eenseestave inspections following servies under AVf eseditions, j

I not incluntag the preservice i-.:;_sen, result is all l

inspection resulte falling Late the C-1 category er if tue ceaseestive inspections dessestrate that pseviously observed I

degradation has not eastissed and as additiemal engradaties has occurred, the inspection interval any be estended to a

==i==a of emee per 40 esoths.

3 I

h.

If the results of the inservies of a steam generater conducted La accordamse with Tab

.4-at 40 anath interamis f all is catepery c-3, the *,:-*= fregnancy shall be inessased to at least sees per 30 months. The ineresse in j

inspectaan tsegeeney obd1 apply until the seseguest i=pania== satisfy the esitoria et speettiestaan 4.4.6.3.as the interval any them he entended to a ansamma et emme par 40 g 463

= * * -

Additiemal, unseeduled isearvies 1-,- -*gshall he c.

orfe d en end s -,at.:

see.

. e m fi,st j

sample inspecties ;, -'**" La Tab

.4-3 sharing the shutdoom subsequent to any of the following conditions:

i De L' criteria is applicable to Cycle 11 enly.

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fansty-umrt 2 3/4 4-11 meussert 30110 i

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REACTOR QJ9.IMIEftRt j,

svRvtILLAncs seguzmEMDrrs (cratiguedi t

j 6.

~ Pluesias or Remair Limit means the imperfectica depth at er; j

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

dettaltion does met apply for tubes that meet the

/L%

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criteria. For a tube that has been sleeved with a

]

anchanical joint sleeve, through wall penetratien of greater j

thaa er equal to 314 et sleeve nonLaal wall thickness in the j

sleeve requires the tube to be removed from service by plugging.

For a tube that has been sleeved with a welded j

j b

t sleeve, through us11 paastraties greater thaa er equal o

j to-8W11f sleeve naminal wall' thickness in the sleeve j

between the weld joints requires the tube to be removed feen i

service by plugging. This definition does met apply to tube i

support plate intersections for which the voltage-based [M i

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

i for the repair limit applicable to these intersections. For a tee with as imperfection er flew in the tubesbeet below the lower $eint of an installed elevated laser welded sleeve, ao repair er plugging is required provided the lastalled sleeve meets all aleeved t h laspecties requirements.

j 7.

Unserviceable describes the condition of a tube er sleeve if j

it leaks er contains a defect large enough to affect its structural integrity in the event of an operating Basis l

Earthquake, a less-of-coolant accident, or a steam line or*

j feedwater line break as specified in 4.4.4.3.c, above.

e 8.

' Tube Inspectica means an inspection of the steen generator tube from the pelat of entry (bet leg sidel cogletely around the U-bend to the top support of the cold leg. 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 i

sleeve joint. For a tube that has been repaired by l

sleeving, the tube inspection should include the sleeved j

porties of the tube.

t 1

j S.

., Tube Depaiy refers to medanteel sleeving, as described by Wes*i-Me report schP-11178. Rev.1, or latser welded i

h/C48-MO N,

sleeving as described by Westinghouse reporwir "% s,- y-i

'"2w 4 %( N m ~!!" ""'.*.*"' '.". 5 ".",""" _-, A

._",...u,' '_ "'" I ! "' _ ! !', ' '. :

s---

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yydAP-/ M which e used to maintain a tubs in servios er retura e tube to service. This includes the reaeval of plugs that were f

installed as a corrective er preventive measure.

j he v e=ia.,1

1..,,ti mt. to ever. it e.xy.

l 889 The elevated tube sheet sleeve is avtberised for installation only during the Unit 2 F.leventh hafueling outage.

rAsLt.r-uurt 2 3/4 4-12a AMemoMaut so. 11F l

0]9 94,10b lid l'$

j t

i

i l

anacres osauert mrm j

gygwggLusges maptagerFS (Case t==41

- 10.

Rameesvies *- - - * = anans as inspection of the 2 41 length of each I

see is osah steses gemesster perdeamos by addy encrust tenmiques prior l

~ te service te establiek a baselias sendities of the tedag. This insposties shan be per9eanad after the field hydrostatic test and prior to initial DOWER OPERAT18FI asiay the egeipment and todmiguas espected j

to be need dassag sehseguess inoasvies iPi==.

11.

is the distamos of the empended parties of a tube eien j

p a sufficient lange of sedegredad tee espansion to seatst pulleet of the tehe from the W. The P distanes is equal to i

1.54 inehas plus ansannes for eddy earsent amenstainty measurement and l

Le== = d deem isen the tap of the tube aheet er the betten of the sell teensities, whishever is louer in stavatism. The alleunsee ter addy surrent unmortaisty is desuesented La the steen generator eddy surrent inspecties preceduss.

12.

@ is a tehes l

a) esith dogsadation ogsel to er prester then 400 helow the F* distamos, and b) ehish has as indienties of layerfassiens greater them er equal to l

204 of aeminal en11 thiekness tatthis the P diseases, med el that l

russias inoesvies.

If the ehese eestasia anaaet he met, them the L* tee esitesia any be opplied or the tee aest he plegged er sepsised.

13.

L* Lemethw is the length of the espanded postiam of the tube into the tube sheet from the bottaa of the neued tsamaities or the tag of the tube sheet, inica over is louer, that has been de*a-iw to be 145 inehes.

14.

L* tube us al is a tee with degradetaan equal er greater then 404 below the L' length and met degraded within the L* 1engths bi the eddy current indienties of degradaties below the L* lamyth inant he detemmined te he the result of cracks isth as oriastaties me greater then 15 degrees fsem asials el the L* sritasia shall be limited to a masiansa of i

600 tube enes per steen generatess di tubes gealifyias as F* tehes ase set classified as L* tubess el a miassume of 3.1 Amakes of me see isee the teesheet fama the tap of takenheet er hottom ed the-sealed transitism, thie seer is lames, shan he taspessed estag sotating peneaks sail ed$ sassent technigen et e inspessien mothed sheen to give egoissiast er hettes infametiam en es asianamef,sa and length of asial essahes fl a minimma aggregate ed 3.87 immes ed scend seu espansions gl a maaisema creek langth of.39 imekees h) a ansiasm of 5 distiast indiastiene with a single head at tes depsedesimas and il that remains is servies.

te L* Czitaria is applicable to cycle 11 enly".

(Y a mLar-aszr 2 3/4 4-te aesmener so. Its gy 4 ( 3N SO

/6 a0

REACTOR COOLAFLEIRIBl SURVEILLANCE REGUIRDWfTS (Contirued) i j

/J # Tube Expansies is that porties et a the which has been Sacreased in diameter by a rolling process such that ne g

erovise exists between the outside diameter of the tube and the hele in the tubesheet. Tube espansion aise refers to j

that portion of a sleeve which has bees increased in dismatar by a rolling process such that se crevice exists l

between the outside diameter of the sleeve and the parent stesa,e.orater tube.

//

Tube Supeert 91ste Reseir Limit is used for the disposition of as alley 600 steen generator tuba for coatiaued service that is emperiencing predominately asially oriented outside diameter stress corrosion cracking confined within the i

thickness of the tube support plates. At tube support plate I

intersections, the repair limit is based on esistaining j

l steam generater tube serviceability as described below:

I Steam generator tubes, whose degradation is attributed a.

to outside diameter stress oorgestem cracking withis

~

the bounds et the tube support plate with hobbia voltages less than er equal to the lower voltage l

repair limit (2.0 welts), will be allowed to remain la servies.

i q

b.

Steam generator tubes, whose degradaties is attributed j

to outside diameter stress corrosion cracking withis the bounds of the tube support plate with a bobbia j

vetrage greater than the lowse voltage repair limit -

l (2.0 volts), will be aired et plugged emeept as l

acted in 4.4.6.4.a below.

/

l steam generator tubes, with indications of potential i

, c.

l degradation attributed to outs &de diameter stress i

l eerresion cracking within the bounds of the tube support plate with a bebbia voltage greater than the i

lower weltage repair limit [3.0 volts) but less thaa l

er equal to the upper voltage repair limit *, may remain in service if a rotating prebe inspecties does l

l not detect degradaties. Steam gemarator tubes, with indications of outside diameter stress sorroeise i

j cracklag degradaties with a behbia wel greater than the g per weltage repair limit *,

be plugged i

er repalted.

The uppec weltage repair limit is calculated seeerding to the methodology in Gamerie Letter 95-09 as supplemoeted.

rAgLgy-trNIT 2 3/4 4-13 AMDfDMENT Wo.117 H m loh (p4)10(9((O US~

il y

1 j

l REAcTom C001AlfT SYSTDI supytILIANG REQUIRDWWTS (Continued) l

.....a..-...-

d.

__12 aa unsehedsled add-sydflaspecties is performed,

__ e__

~

W C, 7 the follouiat a M e repair limits ly instead of 1

i the limits i tified in 4.4.6.4.a.

.a.

4.4.6.4.e.

., and 4.4.6.4.t.ht T 1%e mid-cycle r limits are estessWLeeS rren the Jellowing j

equatieass h

i9i v m=

1... No...

Vam"Vess-IVem-Val I 1

l where i

upper weltage repair limit Vem

=

vm lower weltage repair limit

=

aid-cycle upper voltage repair limit based Vmm

=

i en tima inte cycle mid-eysle lomas weltage repair limit based Vem

=

en %em and time into cycle l

length of time einse last nebedmied At

=

j inspecties during W ah vem and Vm were iglemented cycle length Ithe time between two CL

=

schedaled steen generator inspections) structural limit weltage i

Vm

=

i Gr

=

average growth sete par sysle length l

NDE

=

75-pMM manslative probability i

a11 uaman for sendestructive --*= tion uncertainty ti.e., a value of 20-percent t

has been approved by NRC) i i

laplementatiam of these mid-cycle repair lima bould l

follow the t$ meek as in

.4.6.4.a 4.4.6.4.a

, and 4.4.6.4.a.

/

I

/

a b.

The steen generator shall be de*===dmad Orm attas emepleting I

the es.; _;: "8eg actions (plug er sepair of sti tekee es the plugging er repair 11 mitt required by Tab

4. 4-2 M "3.

4 i

i J

i i

1 I

ransamrasas.a.

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(, q.--o aos ft1f i

i

REACTOR COOLANT SYSTEM SURVEILLANCE REQUImaMENTS (C2ntinuedi

)

4.4.6.5 Reports l

a.

Following each inservice inspection of steam genera t

s, the i

number of tubes plugged, repaired or designated

/ *.. t each steam generator shall be reported to the Coasmission w thin 15 days j

of the completion of the inspecties, plugging or repair effort.

b.

The complete resulta of the steam generator tube and sleeve inservice inspection shall be submitted to the Cometission in a Special Report pursuant to specification 6.9.2 within 12 months i

following the completion of the inspection. This Special Report shall includes i

1.

Number and extent of tubes and sleeves inspected.

2.

Location and percent of wall-thickness penetration for each 1

indicaties of an impetfectaan.

I j

3.

Identification of tubes plugged or repaired.

l l

Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be j

I reported pursuant to 10CFRSO.73 prior to resepties of plant eperaties. The writtaa report shall provide a description of J

investigations conducted to determine the cause of the tube j

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 41 should any of the following conditions arise g

1.

If estimated leakage based on the projected end-of-cycle for i

if not practical, using the actual measured end-of-cyclel j

voltage distribution exceeds the leak limit (determined from the licensing basis dcse calculation for the postulated main stema line breaki 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 estead beyond the

]

confines of the tube support plate.

l 4.

It indications are identified at the tube support plate elevations that are attributable to primary innter stress corrosion erseking.

5.

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

L 58 L* Criteria is applicable to Cycle 11 only.

rAnggy.qartf 2 3/4 4-13b m so. 115 l

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TABLE 4.4-3 STEAM GENERATOR REPAIRED TUBE INSPECTION i

m N

l IST SAMPLE INSPECTION E

2ND SAMPLE INSPECTION Sample Size Result Actions Required E

Result Action Required h

A minimum of C-1 None NA NA 5

20% of repaired tubes N

(1) (2)

C-1 None I

C-2 Plug or repair defective l

repaired tubes and inspect E

100%oftherepairedtubesinl C-2 Plug or repair defective this steam generator.

H repaired tubes.

[

C-3 Perform action for C-3 i

result of first sample.

f C-3 Inspect all repaired tubes in All other steam None this steam generator, plug or generators are

,j, repair defective tubes and C-1.

i p

inspect 20% of the repaired Some steam Perform action for C-2 l

tubes in each steam generator generators C-2 result of first sample.

but no additional Notification to NRC pursuant steam generators j

to 10 CFR 50.72 (b) (2).

are C-3.

i Inspect all repaired tubes

[

IAdditionalstea generator is C-3.

in each steam generator and plug or repair defective tubes.

Notification to NRC i

g pursuant to 10 CFR I

R 50.72(b)(2).

[

M, e

g (1)

Each repair method is considered a separate population for determination of scope expansion.

(2)

The inspection of repaired tubes may be performed on tubes from 1 to 3 steam generators based on outage j

i plans.

a b

t t

m m

(

REACTOR C001MT SYSTEM BASES I

i

• /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 ii maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revasion 1.

InservAce inspecties of steam generator tubing is essential in order to asiatain surveillance of the conditions of the tubes la the event that there is j

evidence of mechanical damage er progressive degradation due to design, f

manuf acturing errors, or Laservice conditions that lead to cerrosion.

Inservice inspection of steam generater tubing also provides a means of characterising the nature and cause of any tube degradation so that corrective i

usasures can be taken.

4 i

The pleat is expected to be operated in a manner such that the secondary 4

f coolant will be maintained within those chemistry lialts found to result in negligible corrosion of the steam generater tubes. If the secondary coolant j

chemistry is not maintained within these limits, localised corrosion may i

j likely result in stress corrosiec cracking. The estaat of cracking during l

plant operation would be limited by the limitation of steam generater tube j

leakage between the primary coolant system and the seesadary coelaat system (primary-to-secondary leakage = 150 gallene per day per steam generateel.

i Cracks having a primary-to-secondary leakage less than thia 11att during operaties wi?1 have an adequate margia of safety to withstand the leads l

imposed during normal operation and by postulated accidents. Operational leakage of this magnitude can be readily detected by esisting yarley Unit 2 radiation monitors. Imakage in excess of this limit will require plant j

shutdown and an unscheduled inspection, during which the leaking tubes will be j

located and plugged or repaired.

/

l The voltage-based repair limits of 4.4.6.4.a.

implement the guidance in GL 95-05 and are applicable only to Westinghouse-designed steam generators (SGs) l with outside diameter stress corrosion cracking (ODSCCI located at the tube-toa.ube support plate intersections. The voltage-based repair limits sse not i

applicable to other forma of SG tube degradation nor are they applicable to i

j CDSCC that occurs at other locations within the SG.

Additionally, the repair criterie apply only to indications where the degradation mechanism is a

dominantly asial CDSCC with no significant cracks estendiaq outside the thickness of the support plate. Refer to GL 95-05 for additiemal description of the degradaties morybology. /

!aplementation of 4.4.6.4.a.

requires a derivaties of the weltage structural limit from the burst versus voltage empirical oestelaties and them the subsequent derivaties of the voltage repair limit f rom the sts--=1 limit (which is then implenosted by this surveillancet.

EmRLar-us1T a a 1/4 4-s Ananasurf me.115 49 k3 Nj NUN j

j 3

j

d 1

REACTOR COOLANT SYSTfM l

wu l

The voltage structural limit is the voltage from the burst pressure / bobbin voltage eerrelaties, at the 95-percent predicties interval curve reduced to account for the lower 95/95-parcent tolerance bound for tubing material 4

properties at 650 'r (i.e., the 95-percent LTL curvel. The voltage structural 3

l 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 V 6,

is determined f rom the structural voltage limit by applying the following equations Vuss = Vss - Var - Vses I

where Vs, represents the allowance for flaw growth between inspections and V.se represents the allowance for potential sources of error in the measurement of the bobbia coil voltage. Further discussion of the assumptions necessary to determine the voltage repair limit er discussed in GL 95-05.

4

{

The mid-cycle equation in 4.4.6.4.a.

should only be used during unplanned j

inspections in which eddy current data is acquired for indications at the tube support plates.

4.4.6.S implements several reporting requirements recoemended by GL 95-05 for situations which the NRC wants to be actified prior to returning the SGs to g

service. For the purposes of this reporting requirement, leakage and l

j conditional burst probability can be calculated based on the as-found voltage distribution rather than the projected end-of-cycle weltage distribution 4

trofer to GL 95-05 for more informatioal when it is not practical to complete these calculations using the projected EOC voltage distributions prior to l

returning the SGs to service. Note that if leakage and conditional burst probability were calculated usiaq the measured 20C voltage distribution for 3

the purposes of addressing the GL section 6.a.1 and 6.a.3 reporting crateria, then the results of the projected EOC voltage distribution should be provided l

per the GL ssetion 6.bici criteria.

Wastage-type defects are unlikely with proper chemistry treatment of the i

secondary coolant. However, even if a defect should develop La service, it j

will be found during scheduled inservice steam generator tube esaminations.

t Fiugging or repair, wall be required for all tubes with isperfections escoeding 40% of the tube nominal well thickness. If a sleeved tube is found to have i

f, through etration of greater thaa er equal to 31% for the mechanical i

sleeve a 37 for the laser welded sleeve of naminal wall thickness in the sleeve must be plugged. The 314 limits are derived from R. G.

1.121 calcursueas with 205 m ser cease an. The porties of the tube and the sleeve for intich indications of wall degradation must be evaluated can j

l be suematised as follows:

I

a. Mechanical 1.

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

j i

{

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.

FAagg-UNIT 2 5 3/4 4-Se N WIBWT Wo. 115 j

b%Q9,9h 9%Ito i

o

{

i

~.

-_e.

Tf?OR

'""=T SYSTEN Wu yhe tube plugging limit osatimoes to apply to the porties cf tha 3.

tube in the entire upper jeLat zegies and in the lower roll

{

As noted above, the sleeve plugging limit applies te espansion.

these areas alse.

The tube pluggiaq limit sentinues to apply to that porties of the 4

tube above the top of.3he upper 3eint.

m.

Laser Weided

)

Indications of degradation la the length of the sleeve between the j

1 wald joista intet be evaluated against the sleeve plugging limit.

l Indication of tube degradaties of any type taciuding a semplete 4

2.

break in the tube between the upper wald joint and the lower weld 3eint does met require that the tube he saneved from service.

At the wald joint, degradatism saast be evaluated in both the l

3.

sleeve and tube.

i In a joint with more than see unid. the weld closest to the end of 4.

the sleese represents the joint to be inspected and the limit of the sleeve 1: ;:-8=.

The tube p'ugging limit eestianos to apply to the portion of the 5.

tube above the upper wald joint and below the lower wald joint.

of the r* tubes de met have to be plugged es sepaized provided the 3 ear tube within the tubesheet that is above the F' distanes is met degraded.

The r* distance is equal to 1.54 saches plus allowanes for eddy current uncertainty esasurement and is asasured down freut the top of the tubasheet er the bottaa of the roll transities, whichever is lower la elevaties.

M L* is similar to r*s however, bands of axial degradaties are allowed as 1 as sufficient nee-degraded tubtag is available to susure structural and leakage 1stegrity. L* criterien is only applicable for Unit 2 Cycle 11.

l Provided below La the Unit 2 Cycle 11 specific L' criterios ANDiEsearT N0. I16 8 3/4 4-3b rARL Y-UNIT 2

@ 7 W )IM II I 3

f

.- =...

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

asAcToa cooLAprr systes aAsts Unit 2 i:ysle 11 spes111s L* Cziteries i

i Parameter Value Minimum distance of SM 2.07 inches Maximum number of distinct degradation areas in a 5

band I

Maximum inclination angle within a single band 15 cegrees j

Maximum crack length

.39 inches l.

Minimum distance of SM f rom the bottom of the 1.45 inches transition roll to the top of the indication steam generator tube inspections of operattag plaats have demonstrated the capability to reliably detect wastage type degradottee that has penettsted 204 of the original tube unit thickness.

i i

Whenever the'results of any steam gecerator tubing inservice inspectaen fall into Category C-3, these results will be reported 2: the Commission pursuant to 10 CyR S0.73 prior to resumpties of plant operaties. seek cases wall be considered by the Commission en a case-by-ease basis and any result in a l

requirement for analysis, laboratory esaminations, tests, additiemal eddy-i current inspecties, and revision to the Teehaisal specifications, if j

necessa3y.

1 4

I i

a d

k a

1 a

1 1

ymatsraagt 3.

B 3/4 4-3e AMENanarr aso. 115 l

t b

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

J 1

1 i

a l

i I

l 1

i 4

J a

1 i

a

~

i i

i Unit 1 Technical Specification Pages e

i Replacement Pages

]

l Page 3/4 4-9 Replace Page 3/4 4-10 Replace Page 3/4 4-11 Replace Page 3/4 4-12 Replace Page 3/4 4-12a Replace Page 3/4 4-13 Replace Page 3/4 4-15a Insert Page B 3/4 4-3a Replace 1

i

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

l 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 T above 200*F.

avg 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 Steam Generator Tube # Sample Selection and Inspection - The steam generator tube ndnimum sample size, inspection result classification, and the corresponding action required shall be as specified in Tables 4.4-2 and 4.4-3.

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 cr'iteria 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. When applying the exceptions of 4.4.6.2.a through 4.4.6.2.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection. 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:

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.

FARLEY-UNIT 1 3/4 4-9 AMENDMENT NQ.

f I

l l

I l

l l

REACTOR COOLANT SYSTEM l

SURVEILLANCE REQUIREMENTS (Continued) l l

l 1.

All nonplugged tubes that previously had dqtectable wall penetrations greater than 206.

1 2.

Tubes in those areas where experience has indicated potential problems.

3.

A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.

If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

4.

Indications left in service as a result of application of l the tube support plate voltage-based repair criteria shall be inspected by bobbin coil probe during all future refueling outages.

The tubes selected as the second and third samples (if required c.

by Tables 4.4-2 and 4.4-3) during each inservice inspection may l be subjected to a partial tube inspection provided:

1.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2.

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

d.

Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.

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

FARLEY-UNIT 1 3/4 4-10 AMENDMENT NO.

I REACTOR COOLANT SYSTEM i

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.

4.4.6.3 Inspection Frequencies - The above required inservice,

inspections of steam generator tubes shall be performed at the following frequencies:

The first inservice inspection shall be performed after 6 a.

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 an steam generator conducted in accordance with Tables 4.4-2 and 4.4-3 l

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 maxihum 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 Tables 1.4-2 and 4.4-3 during l

the shutdown subsequent to any of the following conditions:

1.

Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.7.2.

2.

A seismic occurrence greater than the Operating Basi's Earthquake.

3.

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

4.

A main steam line or feedwater line break.

EARLEY-UNIT 1 3/4 4-11 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 Acceptance Criteria a.

As used in this Specification:

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 conridered 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.

i 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 j

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 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.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 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 RJ.QUIREMENTS (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 1

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 serviceability as described below:

a.

Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion 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.ll.c below.

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

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

The steam generator shall be determined OPERABLE after j

completing the corresponding actions (plug or repair of all i

tubes exceeding the plugging or repair limit) required by j

Tables 4.4-2 and 4.4-3 l

j i

4.4.6.5 Reports l

Following each inservice inspection of steam generator tubes, a.

the number of tubes plugged or repaired in each steam generator shall be reported to the Commission within 15 days of the completion of the 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 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.

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 deterndne 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 NRC staff prior to returning the steam generators 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-I 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.

i 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 i

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 104, notify the NRC and provide an assessment of the safety significance of the occurrence.

FARLEY-UNIT 1 3/4 4-13 AMENDMENT NO.

TABLE 4.4-3 STEAM GENERATOR REPAIRED TUBE INSPECTION M

1ST SAMPLE IBSPECTION 2ND SAMPLE INSPECTION Sample Size Result Arttions Required Result Action Required Q

A minimum of C-1 None NA NA 20% of h

repaired tubes e

(1) (2) s C-2 Plug or repair defective C-1 None repaired tubes and inspect 100% of the repaired tubes in C-2 Plug or repair defective this steam generator.

repaired tubes.

C-3 Perform action for C-3 result of first sample.

C-3 Inspect all repaired tubes in All other steam None this steam generator, plug or generators are repair defective tubes and C-1.

}

inspect 20% of the repaired Some steam Perform action for C-2 tubes in each steam generator generators C-2 result of first sample.

i but no additional Notification to NRC pursuant steam generators O

to 10 CFR 50.72(b)(2).

are C-3.

Additional steam Inspect all repaired tubes generator is C-3.

in each steam generator and plug or repair defective tubes. Notification to NRC pursuant to 10 CFR 50.72 (b) (2).

h (1)

Each repair method is considered a separate population for determination of scope expansion.

g (2)

The inspection of repaired tubes may be performed on tubes from 1 to 3 steam generators based on outage g

plans.

ci Z

?

REACTOR COOLANT SYSTEM BASES The voltage structural limit is 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 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, Vat, is determined from the structural voltage limit by applying the following equation:

Vent = Vst - Va,- Vuos where Va, represents the allowance for flaw growth between inspections and V,or 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 is contained in GL 95-05.

The mid-cycle equation in 4.4.6.4.a.ll.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 in 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 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.

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 sleeve of sleeve nominal wall thickness in the sleeve, it must be plugged. The 31% and 24% lindts 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 summarized as follows:

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

l J

j l

1 i

T 1

4

+

s I

1 i

i a

Unit 2 Technical Specification Pages Replacement Pages Page 3/4 4-9 Replace Page 3/4 4-10 Replace i

Page 3/4 4-11 Replace Page 3/4 4-12a Replace l

Page 3/4/ 4-12b Replace Page 3/4 4-13 Replace Page 3/4 4-13a Replace Page 3/4 4-13b Replace j

Page 3/4 4-15a Insert j

Page B 3/4 4-3 Replace Page B 3/4 4-3a Replace 1

Page B 3/4 4-3b Replace Page B 3/4 4-3c Delete I

q i

r i

i l

REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 4

3.4.6 Each steam generator shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

4 With one or more steam generators inoperable, restore the inoperable generator (s) to OPEFABLE 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.

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 minimtm 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 Tables 4.4-2 and 4.4-3.

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 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 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:

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.

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

1 PEACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 2.

Tubes in these areas where experience has indicated potential problene.

i 3.

A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.

If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

4.

Indications left in service as a result of application of l the tube support plate voltage-based repair criteria shall be inspected by bobbin coil probe during all future refueling outages.

c.

The tubes selected as the second and third samples (if required by Tables 4.4-2 and 4.4-3) during each inservice inspection may l be subjected to a partial tube inspection provided:

1.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2.

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

Implementation of the steam generator tube / tube support plate repair criteria requires a 100 percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold-leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.

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

FARLEY-UNIT 2 3/4 4-10 AMENDMENT NO.

c

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Category InspectLon Results C-1 Less th.an 5h 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 irjpected are degraded tubes.

C-3 More then 10% of the total tubes inspected are degraded

,l 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 j

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 Tables 4.4-2 and 4.4-3.

l l

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, 1

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 j

conducted in accordance with Tables 4.4-2 and 4.4-3 at 40 month l intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in I

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 i

performed on each steam generator in accordance with the first l

sample inspection specified in Tables 4.4-2 and 4.4-3 during l

the shutdown subsequent to any of the following conditions:

EARLEY-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.,

i 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 j

meet the F* criteria.

For a tube that has been sleeved l

with a mechanical joint sleeve, througi 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 j

sleeved with a welded joint sleeve, through wall penetration greater than or equal to 24% of sleeve l

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.14 for l

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 esent 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,,

1 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 la'ser 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 tu'ae 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.

I l

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) j 10.

Preservice Inspection means an inspection of the full i

length of each tube in each steam generator performed by i

eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall 1

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 port, ion 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 j

the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wal) 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 a1so i

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 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 predominately 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 serviceability as described below:

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

REACTOR COOLANT SYSTEM 3

SURVEILLANCE REQUIREMENTS (Continued) 4 a.

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

3 1

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 j

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 4

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 d

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 lindts 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:

V8L

\\%un=

1.0 + NDE + Gr [ CL-At )

CL V n=Vsent-[VunL-V n) [ CL-At ]

ML L

CL The upper voltage repair limit is calculated according to the methodology in Generic Letter 95-05 as supriemented.

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

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) l where Von upper voltage repair lindt

=

lower voltage repair limit

{

Vutt

=

VW;n mid-cycle upper voltage repair limit based on

=

time into cycle Vmn mid-cycle lower voltage repairkiinit based on

=

N%me and time into cycle At length of time since last scheduled

=

inspection during which Vun and V n were t

implemented CL cycle length (the time between two scheduled i

=

steam generator inspections) i Vn structural limit voltage

=

Gr

=

average growth rate per cycle length 95-percent cumulative probability allowance NDE

=

for nondestructive examination uncer.tainty (i.e.,

a value of 20-percent has been 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 Tables 4.4-2 and 4.4-3.

l 4.4.6.5 Reports a.

Following each inservice inspection of steam generator tubes, 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.

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 Peport 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.

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

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-be. sed repair criteri*a 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 idu ttfied at the tube support plate elevations that are att:1butable to primary water stress corrosion cracking.

5.

If the calculated conditional burst probabC.ity based on the projected end-of-cycle (or if not praccAcal, using the actual measured end-of-cycle) voltage distribution exceeds 1 x 10'#, notify the NRC and provide an dssessment of the safety significance of the occurrence.

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

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

i TABLE 4.4-3 i

STEAM GENERATOR REPAIRED TUBE INSPECTION 5

m 1ST SAMPLE INSPECTION l

2ND SAMPLE INSPECTION Sample Size Result Actions Required l

Result Action Required A minimum of C-1 None NA NA E

20% of to repaired tubes (1) (2)

C-2 Plug or repair defective C-1 None repaired tubes and inspect 100% of the repaired tubes in C-2 Plug or repair defective this steam generator.

repaired tubes.

C-3 Perform action for C-3 result of first sample.

{

C-3 Inspect all repab ed tubes in All other steam None this steam generaw, plug or generators are 4

repair defective tubes and C-1.

y inspect 20% of the repaired Some steam Perform action for C-2 l

tubes in each steam generator generators C-2 result of first sample.

but no additional Fotification to NRC pursuant steam generators i

to 10 CFR 50.~12 (b) (2).

are C-3.

IAdditionalstea Inspect all repaired tubes generator is C-3.

in each steam generator and plug or repair defective tubes.

Notification to NRC pursuant to 10 CFR

50. 72 (b) (2).

ci z

(1)

Each repair method is considered a separate population for determination of scope expansion.

(2)

The inspection of repaired tubes may be performed on tubes from 1 to 3 steam generators based on outage plans.

...-... m.-

u

+ -.. e a

+ - -

w-

l 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 j

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 tv degradation so that corrective measures can be taken, i

The plant is expected to be operated in a manner such that the see'ondary coolant will be maintained within those chemistry lindts 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 cperation 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 tuba-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 e'ttending outside the thickners of the support plate.

Refer to GL 95-05 for additional description of the degradation morphology.

Implementation of 4.4.6.4.a.14 requires a derivation of the voltage l

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).

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

l l

l REACTOR COOLANT SYSTEM BASES i

The voltage structural limit is the voltage from the burst pressure / bobbin i

voltage correlation, at the 95-percent prediction interval curve reduced to 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 limit; Vupt, is determined from the structural voltage limit by applying the following equation:

Vun = Vn - Var - Vm l

l where Vor represents the allowance for flaw growth between inspections and l

Vux 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, i

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 4.4.6.5 implements several reporting requirements recommended by GL 95-05 l

for situations which the NRC wants to be notified prior to returning the j

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 fot more information) when it is not j

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 1

l 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.blc) criteria.

l Wastage-type defects are unlikely with 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.

j Plugging or repair will be required for all tubes with imperfections l

exceeding 40% of the tube nominal wall thickness.

If a sleeved tube is j

l found to have through wall penetration of greater than or equal to 31% for l

the mechanical sleeve and 24% for the laser welded sleeve of sleeve nominal l

wall thickness in the sleeve, it must be plugged. The 31% and 24% limits l

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 summarized as follows:

a. Mechanical 1

1.

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

FARLEY-UNIT 2 B 3/4 4-3a AMENDMENT No.

REACTOR COOLANT SYSTEM BASES guillotine break in the tube between the bottom of the upper joint and the top of the lower roll expansion does not require l

that the tube be removed from service.

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 slorve between i

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 j

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 I

i i

l Steam generator tube inspections of operating plants have demonstrated the l

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 f all into Category C-3, these results will be reported to the Comidssion i

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.

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

4 s